ENTRY 23260 20230212 231423260 0 1 SUBENT 23260001 20230212 231423260 1 1 BIB 14 111 23260 1 2 TITLE Experimental determination of k0, Q0 factors, effective23260 1 3 resonance energies and neutron cross-sections for 37 23260 1 4 isotopes of interest in NAA. 23260 1 5 REFERENCE (J,JRN,302,655,2014) Data tables. 23260 1 6 #doi:10.1007/s10967-014-3281-0 23260 1 7 Also Suppl.materials: 23260 1 8 10967-2014-3281-MOESM1-ESM.pdf Exp.details 23260 1 9 10967-2014-3281-MOESM2-ESM.pdf Table -SIG, k0 23260 1 10 10967-2014-3281-MOESM3-ESM.pdf Table -Q0, ef.res.energy23260 1 11 (J,JRN,302,631,2014) Data table for part of isotopes. 23260 1 12 ALPHA-vector method. 23260 1 13 #doi:10.1007/s10967-014-3276-x 23260 1 14 AUTHOR (F.Farina Arbocco,P.Vermaercke,K.Smits,L.Sneyers, 23260 1 15 K.Strijckmans) 23260 1 16 INSTITUTE (2BLGMOL) F.Farina Arbocco,P.Vermaercke,K.Smits, 23260 1 17 L.Sneyers. 23260 1 18 (2BLGGHT) F.Farina Arbocco,K.Strijckmans. 23260 1 19 Samples were prepared at: 23260 1 20 IRMM - Institute for Reference Materials and23260 1 21 Measurements, 23260 1 22 NIST - National Institute of Standards and 23260 1 23 Technology. 23260 1 24 REL-REF (R,,F.De Corte+,J,AND,85,47,2003) 23260 1 25 Activation decay schemes (ADS). 23260 1 26 Summary of previous k0 measurements up to Dec.2002. 23260 1 27 (R,,R.Jacimovic+,J,JRN,300,589,2014) 23260 1 28 Data used in calculations; 23260 1 29 also from : 23260 1 30 - NuDat 2.6: Nuclear Structure and Decay Data. 23260 1 31 http://www.nndc.bnl.gov/nudat2/. Accessed 1 Dec 2013; 23260 1 32 - CEA -Laboratoire National Henri Becquerel (2012) 23260 1 33 Recommended Data. France. Accessed 1 Jun 2013 23260 1 34 http://www.nucleide.org/DDEP-WG/DDEPdata.htm 23260 1 35 for: half-lives, decay branching factors (Fi), 23260 1 36 gamma abundances. 23260 1 37 FACILITY (REAC,2BLGMOL) Irradiation channels S84, Y4, X26 and 23260 1 38 Cavity at the BR1 reactor at SCK-CEN, Belgium. 23260 1 39 INC-SOURCE (REAC) 23260 1 40 INC-SPECT Parameters of the neutron spectra: 23260 1 41 Channel f a 23260 1 42 Y4 38.2+-0.5 0.066+-0.003 23260 1 43 S84 16.4+-0.4 -0.003+-0.005 23260 1 44 X26 95.0+-2.5 0.110+-0.005 23260 1 45 Cavity 70000. (pure thermal) 23260 1 46 f - ratio of the thermal neutron flux to epithermal 23260 1 47 flux, 23260 1 48 a - slope parameter of the epithermal spectrum 23260 1 49 (~1/(E**(1+a)) . 23260 1 50 Thermal neutrons temperature, deg C: 23260 1 51 Y4 - 27, S84 - 50, X26 - 25, thermal Cavity - 23 with 23260 1 52 uncertainty about 7%. 23260 1 53 SAMPLE The liquid standards were spiked on cylindrical 23260 1 54 cellulose filters of 1.25 mm thickness and 7 mm diam., 23260 1 55 with typically 100 microliter of solution content. 23260 1 56 The foils were cut in disks of 8mm diameter (average). 23260 1 57 Packed inside plastic bags of 0.1 mm thick. 23260 1 58 Four samples of each material were prepared and 23260 1 59 irradiated per channel per irradiation exercise. 23260 1 60 Half of these samples were placed along the axis of a 23260 1 61 cylindrical polyethylene irradiation container or 23260 1 62 'rabbit', while the other samples were covered in 23260 1 63 hollow Cd cylinders of 1 mm wall thickness. Inside the 23260 1 64 rabbit, each sample was sandwiched between at least 2 23260 1 65 comparators with a 2 cm separation to each one. The 23260 1 66 comparator consisted in 0.1 % Au Al-alloy foils of 23260 1 67 0.1 mm thickness and 7 mm diameter (IRMM 530R). 23260 1 68 For irradiations in the thermal Cavity, the comparator 23260 1 69 consisted in a high-purity Au wire(Goodfellow 5150/43).23260 1 70 Au-197 samples : 23260 1 71 - Provider - Goodfellow, 23260 1 72 Matrix - wire, 23260 1 73 Elemental content, % weight - 99.99 23260 1 74 Average sample thickness h,mm - 0.5 23260 1 75 - Provider - IRMM 23260 1 76 Matrix - Foil, Al alloy 23260 1 77 Average sample thickness h,mm - 0.1 23260 1 78 - Elemental content, % weight - 0.1 23260 1 79 - Elemental content, % weight - 5. 23260 1 80 METHOD (ACTIV) The rabbits were irradiated under the full 23260 1 81 extent of the neutron flux of channels S84, Y4, X26 and23260 1 82 the thermal Cavity at the BR1. 23260 1 83 Channel Y4 S84 X26 Cavity 23260 1 84 Channel radius 50.mm 40.mm 40.mm 40.mm 23260 1 85 Channel length 500.mm 300.mm 300.mm 300.mm 23260 1 86 Rabbits radius 11.1mm 10.mm 20.mm 15.mm 23260 1 87 Rabbits length 71.mm 53.mm 80.mm 60.mm 23260 1 88 Typical irr.time 429.+-5.m 3600+-2s 180.+-1m 240.+-1m 23260 1 89 The Cd-covered rabbits were irradiated within 30 min, 23260 1 90 1 h and 1 day separation to the normal rabbits for 23260 1 91 channels S84, X26 and Y4, respectively. 23260 1 92 - Lu-176 ( Provider- IRMM, foil,Al alloy, 0.1 % weight,23260 1 93 thickness 0.1mm) was used as temperature monitor; 23260 1 94 neutron self-shielding factors Gtherm=0.998,Gepi=1.000,23260 1 95 Er = 0.158 eV, factor s0=1.76 (+-10%) were adopted . 23260 1 96 ASSUMED (ASSUM,(79-AU-197(N,G)79-AU-198,,RI)/ 23260 1 97 (79-AU-197(N,G)79-AU-198,,SIG)) 23260 1 98 - Au-197 data: Er=5.65 eV (+-7.%), Q0=15.7 (+-2%) ; 23260 1 99 FCd=0.991, HL=2.695d , Gamma Energy 411.8 keV, 23260 1 100 Intensity 95.54%, k0=1.00 . 23260 1 101 DETECTOR (HPGE) Different HPGe detectors attached to Dual LFC 23260 1 102 modules for dead time correction. 23260 1 103 CORRECTION Epithermal and thermal self-shielding corrections 23260 1 104 factors Gt and Ge were obtained through the Chilian+ 23260 1 105 and the MATSSF methods, are given in Table 1 of 23260 1 106 JRN,302,655,2014. 23260 1 107 HISTORY (20141210C) M.M. 23260 1 108 (20151013A) SD: SF4 modified, SF5=M+ added in REACTION 23260 1 109 code in Subents 029, 030, 037, 038, 072, 073, 101, 102,23260 1 110 109, 110. 23260 1 111 (20181012A) SD: Value corrected in Subents 085,142. 23260 1 112 (20230212A) SD: Correction in Subents 135, 136. 23260 1 113 ENDBIB 111 0 23260 1 114 COMMON 2 3 23260 1 115 ASSUM ASSUM-ERR 23260 1 116 NO-DIM PER-CENT 23260 1 117 15.7 0.1 23260 1 118 ENDCOMMON 3 0 23260 1 119 ENDSUBENT 118 0 23260 199999 SUBENT 23260002 20141210 224123260 2 1 BIB 8 38 23260 2 2 REACTION ((19-K-41(N,G)19-K-42,,RI)// 23260 2 3 (19-K-41(N,G)19-K-42,,SIG)) 23260 2 4 Q0 value (ratio of resonance integral to thermal 23260 2 5 neutron activation cross-section) 23260 2 6 SAMPLE Provider - Alfa Aesar, 23260 2 7 Matrix - Liquid on paper, 23260 2 8 Elemental content, % weight - 0.1 23260 2 9 Average sample thickness h,mm - 1.25 23260 2 10 DECAY-DATA (19-K-42,12.36HR,DG,312.7,0.00336,DG,1524.7,0.1808) 23260 2 11 METHOD Measurement at Y4 channel. 23260 2 12 ANALYSIS The Q0(or s0) factor was determined by 23260 2 13 - the classical method: from the mean (AVG) and 23260 2 14 observed SD of the results from all channels employed, 23260 2 15 when inputting the recommended Er value from 23260 2 16 references - 2960 eV (+-7%) 23260 2 17 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 2 18 Uncertainty in the Q0 determination for for the simple 23260 2 19 case of one determination in one irradiation channel 23260 2 20 with one standard, given no type-B uncertainties 23260 2 21 contributions from the FCd = 1 and neutron 23260 2 22 self-shielding effects is on average 23260 2 23 2.5 % for foils, 2.6 % for compounds; 23260 2 24 include contributions from : 23260 2 25 - The combined uncertainty 1.2 % 23260 2 26 for liquids/compounds in the parameter OMEGACd . 23260 2 27 - A combined type-B uncertainty of from the 23260 2 28 comparator Qa factor 1.9 % . 23260 2 29 - A combined type-B uncertainty of 1.2 % during 23260 2 30 Qa -> Q0 conversion, due to the uncertainty on a and 23260 2 31 an average 7 % uncertainty on the recommended effective23260 2 32 resonance energy factor for the analyte, taken from 23260 2 33 references. 23260 2 34 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 2 35 E-gamma,keV k0, no-dim. 23260 2 36 312.7 1.75E-5 (+-1.9%) 23260 2 37 1524.7 9.45E-4 (+-1.9%) 23260 2 38 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 2 39 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 2 40 ENDBIB 38 0 23260 2 41 COMMON 2 3 23260 2 42 EN-MIN-NM EN-MEAN-DN 23260 2 43 EV EV 23260 2 44 0.5 0.0253 23260 2 45 ENDCOMMON 3 0 23260 2 46 DATA 2 1 23260 2 47 DATA DATA-ERR 23260 2 48 NO-DIM PER-CENT 23260 2 49 0.74 4. 23260 2 50 ENDDATA 3 0 23260 2 51 ENDSUBENT 50 0 23260 299999 SUBENT 23260003 20141210 224123260 3 1 BIB 9 46 23260 3 2 REACTION 1((24-CR-50(N,G)24-CR-51,,RI)// 23260 3 3 (24-CR-50(N,G)24-CR-51,,SIG)) 23260 3 4 2((24-CR-50(N,G)24-CR-51,,RI)// 23260 3 5 (24-CR-50(N,G)24-CR-51,,SIG)) 23260 3 6 Q0 value (ratio of resonance integral to thermal 23260 3 7 neutron activation cross-section) 23260 3 8 SAMPLE Provider - Goodfellow IRMM 23260 3 9 Matrix - Slab Foil,Al Alloy23260 3 10 Elemental content, % weight > 99.99 10. 23260 3 11 Average sample thickness h,mm - 0.05 0.8 23260 3 12 DECAY-DATA (24-CR-51,27.7D,DG,320.1,0.0991) 23260 3 13 METHOD Measurements at S84, Y4 channels. 23260 3 14 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 3 15 approaches: 23260 3 16 1- the classical method: from the mean (AVG) and 23260 3 17 observed SD of the results from all channels employed, 23260 3 18 when inputting the recommended Er value from 23260 3 19 references - 7530 eV (+-16%). 23260 3 20 2- the a-vector method applied on up to 3 irradiation 23260 3 21 channels: leading to simultaneous Q0 (or s0) and Er 23260 3 22 determination; 23260 3 23 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 3 24 method. 23260 3 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 3 26 Uncertainty in the Q0 determination for for the simple 23260 3 27 case of one determination in one irradiation channel 23260 3 28 with one standard, given no type-B uncertainties 23260 3 29 contributions from the FCd = 1 and neutron 23260 3 30 self-shielding effects is on average 23260 3 31 2.5 % for foils, - 2.6 % for compounds; 23260 3 32 include contributions from : 23260 3 33 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 3 34 for liquids/compounds in the parameter OMEGACd . 23260 3 35 - A combined type-B uncertainty of from the 23260 3 36 comparator Qa factor 1.9 % for Y4 and 1.8 % for S84. 23260 3 37 - A combined type-B uncertainty of 1.2 % during 23260 3 38 Qa -> Q0 conversion, due to the uncertainty on a and 23260 3 39 an average 7 % uncertainty on the recommended effective23260 3 40 resonance energy factor for the analysis, taken from 23260 3 41 references. 23260 3 42 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 3 43 E-gamma,keV k0, no-dim. 23260 3 44 320.1 2.49E-3 (+-1.3%) 23260 3 45 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 3 46 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 3 47 1(DEP,23260004) Measured values at two channels. 23260 3 48 ENDBIB 46 0 23260 3 49 COMMON 2 3 23260 3 50 EN-MIN-NM EN-MEAN-DN 23260 3 51 EV EV 23260 3 52 0.5 0.0253 23260 3 53 ENDCOMMON 3 0 23260 3 54 DATA 6 1 23260 3 55 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 3 56 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 3 57 0.48 2. 0.46 3. 0.027 25. 23260 3 58 ENDDATA 3 0 23260 3 59 ENDSUBENT 58 0 23260 399999 SUBENT 23260004 20141210 224123260 4 1 BIB 7 35 23260 4 2 REACTION 1((24-CR-50(N,G)24-CR-51,,RI)// 23260 4 3 (24-CR-50(N,G)24-CR-51,,SIG)) 23260 4 4 2((24-CR-50(N,G)24-CR-51,,RI)// 23260 4 5 (24-CR-50(N,G)24-CR-51,,SIG)) 23260 4 6 Q0 value (ratio of resonance integral to thermal 23260 4 7 neutron activation cross-section) 23260 4 8 SAMPLE Provider - Goodfellow IRMM 23260 4 9 Matrix Slab Foil,Al Alloy23260 4 10 Elemental content, % weight >99.99 10. 23260 4 11 Average sample thickness h,mm 0.05 0.8 23260 4 12 DECAY-DATA (24-CR-51,27.7D,DG,320.1,0.0991) 23260 4 13 METHOD Measurements at channels: 23260 4 14 1 S84 23260 4 15 2 Y4 . 23260 4 16 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 4 17 recommended Er value from references - 7530 eV (+-16%).23260 4 18 ERR-ANALYS (DATA-ERR) Standard deviation. 23260 4 19 Uncertainty in the Q0 determination for for the simple 23260 4 20 case of one determination in one irradiation channel 23260 4 21 with one standard, given no type-B uncertainties 23260 4 22 contributions from the FCd = 1 and neutron 23260 4 23 self-shielding effects is on average 23260 4 24 2.5 % for foils, 2.6 % for compounds; 23260 4 25 include contributions from : 23260 4 26 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 4 27 for liquids/compounds in the parameter OMEGACd . 23260 4 28 - A combined type-B uncertainty from the comparator Qa 23260 4 29 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 4 30 - A combined type-B uncertainty of 1.2 % during 23260 4 31 Qa -> Q0 conversion, due to the uncertainty on a and 23260 4 32 an average 7 % uncertainty on the recommended effective23260 4 33 resonance energy factor for the analyte, taken from 23260 4 34 references. 23260 4 35 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf. 23260 4 36 (COREL,23260003) Average Q0. 23260 4 37 ENDBIB 35 0 23260 4 38 COMMON 2 3 23260 4 39 EN-MIN-NM EN-MEAN-DN 23260 4 40 EV EV 23260 4 41 0.5 0.0253 23260 4 42 ENDCOMMON 3 0 23260 4 43 DATA 4 1 23260 4 44 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 4 45 NO-DIM PER-CENT NO-DIM PER-CENT 23260 4 46 0.46 2. 0.50 2. 23260 4 47 ENDDATA 3 0 23260 4 48 ENDSUBENT 47 0 23260 499999 SUBENT 23260005 20141210 224123260 5 1 BIB 9 41 23260 5 2 REACTION ((38-SR-84(N,G)38-SR-85-M,,RI)// 23260 5 3 (38-SR-84(N,G)38-SR-85-M,,SIG)) 23260 5 4 Q0 value (ratio of resonance integral to thermal 23260 5 5 neutron activation cross-section) 23260 5 6 SAMPLE - Provider - Sigma-Aldrich 23260 5 7 Matrix - SrCO(3) 23260 5 8 Elemental content, % weight - 59.351 23260 5 9 - Average sample thickness h,mm - 0.2 23260 5 10 - Average sample thickness h,mm - 0.6 23260 5 11 DECAY-DATA (38-SR-85-M,67.63MIN,DG,151.2,0.123,DG,231.9,0.841) 23260 5 12 METHOD Measurements at channel S84. 23260 5 13 ANALYSIS The Q0(or s0) factors were determined by 23260 5 14 - the classical method: from the mean (AVG) and 23260 5 15 observed SD of the results from all channels employed, 23260 5 16 when inputting the recommended Er value from 23260 5 17 references - 469.eV (+-7%). 23260 5 18 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 5 19 Uncertainty in the Q0 determination for for the simple 23260 5 20 case of one determination in one irradiation channel 23260 5 21 with one standard, given no type-B uncertainties 23260 5 22 contributions from the FCd = 1 and neutron 23260 5 23 self-shielding effects is on average 23260 5 24 2.6 % for compounds; 23260 5 25 include contributions from : 23260 5 26 - The combined uncertainty of 1.2 % 23260 5 27 for liquids/compounds in the parameter OMEGACd . 23260 5 28 - A combined type-B uncertainty from the comparator Qa 23260 5 29 factor for channel S84 - 1.8 % . 23260 5 30 - A combined type-B uncertainty of 1.2 % during 23260 5 31 Qa -> Q0 conversion, due to the uncertainty on a and 23260 5 32 an average 7 % uncertainty on the recommended effective23260 5 33 resonance energy factor for the analyte, taken from 23260 5 34 references. 23260 5 35 COMMENT Of compiler. DATA uncertainty in Table 5 of 23260 5 36 J,JRN,302,655,2014 is 5.% . 23260 5 37 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 5 38 E-gamma,keV k0, no-dim. 23260 5 39 151.2 1.08E-5 (+-1.9%) 23260 5 40 231.9 7.43E-5 (+-2.0%) 23260 5 41 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 5 42 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 5 43 ENDBIB 41 0 23260 5 44 COMMON 2 3 23260 5 45 EN-MIN-NM EN-MEAN-DN 23260 5 46 EV EV 23260 5 47 0.5 0.0253 23260 5 48 ENDCOMMON 3 0 23260 5 49 DATA 2 1 23260 5 50 DATA DATA-ERR 23260 5 51 NO-DIM PER-CENT 23260 5 52 13.0 3. 23260 5 53 ENDDATA 3 0 23260 5 54 ENDSUBENT 53 0 23260 599999 SUBENT 23260006 20141210 224123260 6 1 BIB 9 49 23260 6 2 REACTION 1((38-SR-84(N,G)38-SR-85-G,(M),RI)// 23260 6 3 (38-SR-84(N,G)38-SR-85-G,(M),SIG)) 23260 6 4 2((38-SR-84(N,G)38-SR-85-G,(M),RI)// 23260 6 5 (38-SR-84(N,G)38-SR-85-G,(M),SIG)) 23260 6 6 Q0 value (ratio of resonance integral to thermal 23260 6 7 neutron activation cross-section) 23260 6 8 SAMPLE - Provider - Sigma-Aldrich 23260 6 9 Matrix - SrCO(3) 23260 6 10 Elemental content, % weight - 59.351 23260 6 11 - Average sample thickness h,mm - 0.2 23260 6 12 - Average sample thickness h,mm - 0.6 23260 6 13 DECAY-DATA (38-SR-85-G,64.84D,DG,514.0,0.985) 23260 6 14 METHOD Measurements at channels: 23260 6 15 S84 23260 6 16 Y4 . 23260 6 17 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 6 18 approaches: 23260 6 19 1- the classical method: from the mean (AVG) and 23260 6 20 observed SD of the results from all channels employed, 23260 6 21 when inputting the recommended Er value from 23260 6 22 references . 23260 6 23 2- the a-vector method applied on up to 3 irradiation 23260 6 24 channels: leading to simultaneous Q0 (or s0) and Er 23260 6 25 determination; 23260 6 26 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 6 27 method. 23260 6 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 6 29 Uncertainty in the Q0 determination for for the simple 23260 6 30 case of one determination in one irradiation channel 23260 6 31 with one standard, given no type-B uncertainties 23260 6 32 contributions from the FCd = 1 and neutron 23260 6 33 self-shielding effects is on average 23260 6 34 2.6 % for compounds; 23260 6 35 include contributions from : 23260 6 36 - The combined uncertainty 1.2 % 23260 6 37 for liquids/compounds in the parameter OMEGACd . 23260 6 38 - A combined type-B uncertainty from the comparator Qa 23260 6 39 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 6 40 - A combined type-B uncertainty of 1.2 % during 23260 6 41 Qa -> Q0 conversion, due to the uncertainty on a and 23260 6 42 an average 7 % uncertainty on the recommended effective23260 6 43 resonance energy factor for the analyte, taken from 23260 6 44 references. 23260 6 45 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 6 46 E-gamma,keV k0, no-dim. 23260 6 47 514.0 9.21E-5 (+-1.9%) 23260 6 48 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 6 49 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 6 50 1(DEP,23260007) Measurement at two channels. 23260 6 51 ENDBIB 49 0 23260 6 52 COMMON 2 3 23260 6 53 EN-MIN-NM EN-MEAN-DN 23260 6 54 EV EV 23260 6 55 0.5 0.0253 23260 6 56 ENDCOMMON 3 0 23260 6 57 DATA 6 1 23260 6 58 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 6 59 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 6 60 14.5 2. 14.6 2. 506. 25. 23260 6 61 ENDDATA 3 0 23260 6 62 ENDSUBENT 61 0 23260 699999 SUBENT 23260007 20141210 224123260 7 1 BIB 7 36 23260 7 2 REACTION 1((38-SR-84(N,G)38-SR-85-G,(M),RI)// 23260 7 3 (38-SR-84(N,G)38-SR-85-G,(M),SIG)) 23260 7 4 2((38-SR-84(N,G)38-SR-85-G,(M),RI)// 23260 7 5 (38-SR-84(N,G)38-SR-85-G,(M),SIG)) 23260 7 6 Q0 value (ratio of resonance integral to thermal 23260 7 7 neutron activation cross-section) 23260 7 8 SAMPLE - Provider - Sigma-Aldrich 23260 7 9 Matrix - SrCO(3) 23260 7 10 Elemental content, % weight - 59.351 23260 7 11 - Average sample thickness h,mm - 0.2 23260 7 12 - Average sample thickness h,mm - 0.6 23260 7 13 DECAY-DATA (38-SR-85-G,64.84D,DG,514.0,0.985) 23260 7 14 METHOD Measurements at channels: 23260 7 15 1 S84 23260 7 16 2 Y4 . 23260 7 17 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 7 18 recommended Er value from references . 23260 7 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 7 20 Uncertainty in the Q0 determination for for the simple 23260 7 21 case of one determination in one irradiation channel 23260 7 22 with one standard, given no type-B uncertainties 23260 7 23 contributions from the FCd = 1 and neutron 23260 7 24 self-shielding effects is on average 23260 7 25 2.6 % for compounds; 23260 7 26 include contributions from : 23260 7 27 - The combined uncertainty of 1.2 % 23260 7 28 for liquids/compounds in the parameter OMEGACd . 23260 7 29 - A combined type-B uncertainty from the comparator Qa 23260 7 30 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 7 31 - A combined type-B uncertainty of 1.2 % during 23260 7 32 Qa -> Q0 conversion, due to the uncertainty on a and 23260 7 33 an average 7 % uncertainty on the recommended effective23260 7 34 resonance energy factor for the analyte, taken from 23260 7 35 references. 23260 7 36 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 7 37 (COREL,23260006) Average Q0 . 23260 7 38 ENDBIB 36 0 23260 7 39 COMMON 2 3 23260 7 40 EN-MIN-NM EN-MEAN-DN 23260 7 41 EV EV 23260 7 42 0.5 0.0253 23260 7 43 ENDCOMMON 3 0 23260 7 44 DATA 4 1 23260 7 45 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 7 46 NO-DIM PER-CENT NO-DIM PER-CENT 23260 7 47 14.6 4. 14.5 2. 23260 7 48 ENDDATA 3 0 23260 7 49 ENDSUBENT 48 0 23260 799999 SUBENT 23260008 20141210 224123260 8 1 BIB 9 49 23260 8 2 REACTION 1((38-SR-86(N,G)38-SR-87-M,,RI)// 23260 8 3 (38-SR-86(N,G)38-SR-87-M,,SIG)) 23260 8 4 2((38-SR-86(N,G)38-SR-87-M,,RI)// 23260 8 5 (38-SR-86(N,G)38-SR-87-M,,SIG)) 23260 8 6 Q0 value (ratio of resonance integral to thermal 23260 8 7 neutron activation cross-section) 23260 8 8 SAMPLE - Provider - Sigma-Aldrich 23260 8 9 Matrix - SrCO(3) 23260 8 10 Elemental content, % weight - 59.351 23260 8 11 - Average sample thickness h,mm - 0.2 23260 8 12 - Average sample thickness h,mm - 0.6 23260 8 13 DECAY-DATA (38-SR-87-M,2.803HR,DG,388.5,0.824) 23260 8 14 METHOD Measurements at channels: 23260 8 15 S84 23260 8 16 Y4 . 23260 8 17 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 8 18 approaches: 23260 8 19 1- the classical method: from the mean (AVG) and 23260 8 20 observed SD of the results from all channels employed, 23260 8 21 when inputting the recommended Er value from 23260 8 22 references - 795. eV (+-2%). 23260 8 23 2- the a-vector method applied on up to 3 irradiation 23260 8 24 channels: leading to simultaneous Q0 (or s0) and Er 23260 8 25 determination. 23260 8 26 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 8 27 method. 23260 8 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 8 29 Uncertainty in the Q0 determination for for the simple 23260 8 30 case of one determination in one irradiation channel 23260 8 31 with one standard, given no type-B uncertainties 23260 8 32 contributions from the FCd = 1 and neutron 23260 8 33 self-shielding effects is on average 23260 8 34 2.6 % for compounds; 23260 8 35 include contributions from : 23260 8 36 - The combined uncertainty of 1.2 % 23260 8 37 for liquids/compounds in the parameter OMEGACd . 23260 8 38 - A combined type-B uncertainty from the comparator Qa 23260 8 39 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 8 40 - A combined type-B uncertainty of 1.2 % during 23260 8 41 Qa -> Q0 conversion, due to the uncertainty on a and 23260 8 42 an average 7 % uncertainty on the recommended effective23260 8 43 resonance energy factor for the analyte, taken from 23260 8 44 references. 23260 8 45 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 8 46 E-gamma,keV k0, no-dim. 23260 8 47 388.5 1.54E-3 (+-2.0%) 23260 8 48 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 8 49 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 8 50 1(DEP,23260009) Measurements at two channels. 23260 8 51 ENDBIB 49 0 23260 8 52 COMMON 2 3 23260 8 53 EN-MIN-NM EN-MEAN-DN 23260 8 54 EV EV 23260 8 55 0.5 0.0253 23260 8 56 ENDCOMMON 3 0 23260 8 57 DATA 6 1 23260 8 58 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 8 59 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 8 60 4.04 2. 3.95 2. 502. 25. 23260 8 61 ENDDATA 3 0 23260 8 62 ENDSUBENT 61 0 23260 899999 SUBENT 23260009 20141210 224123260 9 1 BIB 7 36 23260 9 2 REACTION 1((38-SR-86(N,G)38-SR-87-M,,RI)// 23260 9 3 (38-SR-86(N,G)38-SR-87-M,,SIG)) 23260 9 4 2((38-SR-86(N,G)38-SR-87-M,,RI)// 23260 9 5 (38-SR-86(N,G)38-SR-87-M,,SIG)) 23260 9 6 Q0 value (ratio of resonance integral to thermal 23260 9 7 neutron activation cross-section) 23260 9 8 SAMPLE - Provider - Sigma-Aldrich 23260 9 9 Matrix - SrCO(3) 23260 9 10 Elemental content, % weight - 59.351 23260 9 11 - Average sample thickness h,mm - 0.2 23260 9 12 - Average sample thickness h,mm - 0.6 23260 9 13 DECAY-DATA (38-SR-87-M,2.803HR,DG,388.5,0.824) 23260 9 14 METHOD Measurements at channels: 23260 9 15 1 S84 23260 9 16 2 Y4 . 23260 9 17 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 9 18 recommended Er value from references - 795. eV (+-2%). 23260 9 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 9 20 Uncertainty in the Q0 determination for for the simple 23260 9 21 case of one determination in one irradiation channel 23260 9 22 with one standard, given no type-B uncertainties 23260 9 23 contributions from the FCd = 1 and neutron 23260 9 24 self-shielding effects is on average 23260 9 25 2.6 % for compounds; 23260 9 26 include contributions from : 23260 9 27 - The combined uncertainty of 1.2 % 23260 9 28 for liquids/compounds in the parameter OMEGACd . 23260 9 29 - A combined type-B uncertainty from the comparator Qa 23260 9 30 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 9 31 - A combined type-B uncertainty of 1.2 % during 23260 9 32 Qa -> Q0 conversion, due to the uncertainty on a and 23260 9 33 an average 7 % uncertainty on the recommended effective23260 9 34 resonance energy factor for the analyte, taken from 23260 9 35 references. 23260 9 36 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 9 37 (COREL,23260008) Average Q0 . 23260 9 38 ENDBIB 36 0 23260 9 39 COMMON 2 3 23260 9 40 EN-MIN-NM EN-MEAN-DN 23260 9 41 EV EV 23260 9 42 0.5 0.0253 23260 9 43 ENDCOMMON 3 0 23260 9 44 DATA 4 1 23260 9 45 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 9 46 NO-DIM PER-CENT NO-DIM PER-CENT 23260 9 47 3.97 2. 4.06 1. 23260 9 48 ENDDATA 3 0 23260 9 49 ENDSUBENT 48 0 23260 999999 SUBENT 23260010 20141210 224123260 10 1 BIB 8 51 23260 10 2 REACTION ((42-MO-100(N,G)42-MO-101,,RI)// 23260 10 3 (42-MO-100(N,G)42-MO-101,,SIG)) 23260 10 4 Q0 value (ratio of resonance integral to thermal 23260 10 5 neutron activation cross-section) 23260 10 6 SAMPLE Provider - Goodfellow 23260 10 7 Matrix - Foil 23260 10 8 Elemental content, % weight - 99.9 23260 10 9 Average sample thickness h,mm - 0.025 23260 10 10 DECAY-DATA (42-MO-101,14.61MIN,DG,191.9,0.1821,DG,505.1,0.1162, 23260 10 11 DG,590.1,0.205,DG,695.6,0.665,DG,1011.1,0.146) 23260 10 12 (43-TC-101,14.2MIN,DG,127.2,0.0263,DG,184.1,0.0160, 23260 10 13 DG,306.8,0.890,DG,545.1,0.0596) 23260 10 14 METHOD Measurements at channel: 23260 10 15 S84 via Mo-101 23260 10 16 S84 via Tc-101 23260 10 17 ANALYSIS The Q0(or s0) factors were determined by 23260 10 18 - the classical method: from the mean (AVG) and 23260 10 19 observed SD of the results from all channels employed, 23260 10 20 when inputting the recommended Er value from 23260 10 21 references - 672.eV (+-14%). 23260 10 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 10 23 Uncertainty in the Q0 determination for for the simple 23260 10 24 case of one determination in one irradiation channel 23260 10 25 with one standard, given no type-B uncertainties 23260 10 26 contributions from the FCd = 1 and neutron 23260 10 27 self-shielding effects is on average 23260 10 28 2.5 % for foils, 23260 10 29 include contributions from : 23260 10 30 - The combined uncertainty of 1.1 % for foils 23260 10 31 in the parameter OMEGACd . 23260 10 32 - A combined type-B uncertainty from the comparator Qa 23260 10 33 factor for channel S84 - 1.8 % . 23260 10 34 - A combined type-B uncertainty of 1.2 % during 23260 10 35 Qa -> Q0 conversion, due to the uncertainty on a and 23260 10 36 an average 7 % uncertainty on the recommended effective23260 10 37 resonance energy factor for the analyte, taken from 23260 10 38 references. 23260 10 39 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 10 40 E-gamma,keV k0, no-dim. 23260 10 41 191.9 7.82E-5 (+-1.9%) 23260 10 42 505.1 4.98E-5 (+-1.9%) 23260 10 43 590.1 8.76E-5 (+-1.9%) 23260 10 44 695.6 2.85E-5 (+-1.9%) 23260 10 45 1011.1 6.29E-5 (+-1.9%) 23260 10 46 127.2 1.23E-5 (+-1.9%) 23260 10 47 184.1 6.88E-6 (+-1.9%) 23260 10 48 306.8 3.83E-4 (+-1.9%) 23260 10 49 545.1 2.56E-5 (+-1.9%) 23260 10 50 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 10 51 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 10 52 (DEP,23260012) Measurements used in averaging. 23260 10 53 ENDBIB 51 0 23260 10 54 COMMON 2 3 23260 10 55 EN-MIN-NM EN-MEAN-DN 23260 10 56 EV EV 23260 10 57 0.5 0.0253 23260 10 58 ENDCOMMON 3 0 23260 10 59 DATA 2 1 23260 10 60 DATA DATA-ERR 23260 10 61 NO-DIM PER-CENT 23260 10 62 19.9 2. 23260 10 63 ENDDATA 3 0 23260 10 64 ENDSUBENT 63 0 23260 1099999 SUBENT 23260011 20141210 224123260 11 1 BIB 7 38 23260 11 2 REACTION 1((42-MO-100(N,G)42-MO-101,,RI)// 23260 11 3 (42-MO-100(N,G)42-MO-101,,SIG)) 23260 11 4 2((42-MO-100(N,G)42-MO-101,,RI)// 23260 11 5 (42-MO-100(N,G)42-MO-101,,SIG)) 23260 11 6 Q0 value (ratio of resonance integral to thermal 23260 11 7 neutron activation cross-section) 23260 11 8 SAMPLE Provider - Goodfellow 23260 11 9 Matrix - Foil 23260 11 10 Elemental content, % weight - 99.9 23260 11 11 Average sample thickness h,mm - 0.025 23260 11 12 DECAY-DATA1(42-MO-101,14.61MIN,DG,191.9,0.1821,DG,505.1,0.1162, 23260 11 13 DG,590.1,0.205,DG,695.6,0.665,DG,1011.1,0.146) 23260 11 14 2(43-TC-101,14.2MIN,DG,127.2,0.0263,DG,184.1,0.0160, 23260 11 15 DG,306.8,0.890,DG,545.1,0.0596) 23260 11 16 METHOD Measurements at channel: 23260 11 17 1 S84 via Mo-101 23260 11 18 2 S84 via Tc-101 23260 11 19 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 11 20 recommended Er value from references - 672.eV (+-14%). 23260 11 21 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 11 22 Uncertainty in the Q0 determination for for the simple 23260 11 23 case of one determination in one irradiation channel 23260 11 24 with one standard, given no type-B uncertainties 23260 11 25 contributions from the FCd = 1 and neutron 23260 11 26 self-shielding effects is on average 23260 11 27 2.5 % for foils, 23260 11 28 include contributions from : 23260 11 29 - The combined uncertainty of 1.1 % for foils 23260 11 30 in the parameter OMEGACd . 23260 11 31 - A combined type-B uncertainty from the comparator Qa 23260 11 32 factor for channels S84 - 1.8 % . 23260 11 33 - A combined type-B uncertainty of 1.2 % during 23260 11 34 Qa -> Q0 conversion, due to the uncertainty on a and 23260 11 35 an average 7 % uncertainty on the recommended effective23260 11 36 resonance energy factor for the analyte, taken from 23260 11 37 references. 23260 11 38 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 11 39 (COREL,23260011) Average Q0 . 23260 11 40 ENDBIB 38 0 23260 11 41 COMMON 2 3 23260 11 42 EN-MIN-NM EN-MEAN-DN 23260 11 43 EV EV 23260 11 44 0.5 0.0253 23260 11 45 ENDCOMMON 3 0 23260 11 46 DATA 4 1 23260 11 47 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 11 48 NO-DIM PER-CENT NO-DIM PER-CENT 23260 11 49 19.9 1. 19.9 1. 23260 11 50 ENDDATA 3 0 23260 11 51 ENDSUBENT 50 0 23260 1199999 SUBENT 23260012 20141210 224123260 12 1 BIB 9 53 23260 12 2 REACTION 1((44-RU-96(N,G)44-RU-97,,RI)// 23260 12 3 (44-RU-96(N,G)44-RU-97,,SIG)) 23260 12 4 2((44-RU-96(N,G)44-RU-97,,RI)// 23260 12 5 (44-RU-96(N,G)44-RU-97,,SIG)) 23260 12 6 Q0 value (ratio of resonance integral to thermal 23260 12 7 neutron activation cross-section) 23260 12 8 SAMPLE - Provider - Alfa Aesar 23260 12 9 Matrix - Foil,Pt Alloy 23260 12 10 Elemental content, % weight - 4.6 23260 12 11 Average sample thickness h,mm - 0.05 23260 12 12 - Provider - Alfa Aesar 23260 12 13 Matrix - Liquid on paper 23260 12 14 Elemental content, % weight - 0.1 23260 12 15 Average sample thickness h,mm - 1.25 23260 12 16 DECAY-DATA (44-RU-97,2.9D,DG,215.7,0.856,DG,324.5,0.1079) 23260 12 17 METHOD Measurements at channels: 23260 12 18 S84 23260 12 19 Y4 . 23260 12 20 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 12 21 approaches: 23260 12 22 1- the classical method: from the mean (AVG) and 23260 12 23 observed SD of the results from all channels employed, 23260 12 24 when inputting the recommended Er value from 23260 12 25 references - 776. eV (+-16%). 23260 12 26 2- the a-vector method applied on up to 3 irradiation 23260 12 27 channels: leading to simultaneous Q0 (or s0) and Er 23260 12 28 determination. 23260 12 29 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 12 30 method. 23260 12 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 12 32 Uncertainty in the Q0 determination for for the simple 23260 12 33 case of one determination in one irradiation channel 23260 12 34 with one standard, given no type-B uncertainties 23260 12 35 contributions from the FCd = 1 and neutron 23260 12 36 self-shielding effects is on average 23260 12 37 2.5 % for foils, 2.6 % for compounds; 23260 12 38 include contributions from : 23260 12 39 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 12 40 for liquids/compounds in the parameter OMEGACd . 23260 12 41 - A combined type-B uncertainty from the comparator Qa 23260 12 42 factor for channels S84 - 1.8 % . 23260 12 43 - A combined type-B uncertainty of 1.2 % during 23260 12 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 12 45 an average 7 % uncertainty on the recommended effective23260 12 46 resonance energy factor for the analyte, taken from 23260 12 47 references. 23260 12 48 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 12 49 E-gamma,keV k0, no-dim. 23260 12 50 215.7 2.43E-4 (+-1.3%) 23260 12 51 324.5 3.06E-5 (+-1.3%) 23260 12 52 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 12 53 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 12 54 (DEP,23260014) Measurements at two channels. 23260 12 55 ENDBIB 53 0 23260 12 56 COMMON 2 3 23260 12 57 EN-MIN-NM EN-MEAN-DN 23260 12 58 EV EV 23260 12 59 0.5 0.0253 23260 12 60 ENDCOMMON 3 0 23260 12 61 DATA 6 1 23260 12 62 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 12 63 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 12 64 25.6 2. 26.2 2. 1343. 25. 23260 12 65 ENDDATA 3 0 23260 12 66 ENDSUBENT 65 0 23260 1299999 SUBENT 23260013 20141210 224123260 13 1 BIB 7 39 23260 13 2 REACTION 1((44-RU-96(N,G)44-RU-97,,RI)// 23260 13 3 (44-RU-96(N,G)44-RU-97,,SIG)) 23260 13 4 2((44-RU-96(N,G)44-RU-97,,RI)// 23260 13 5 (44-RU-96(N,G)44-RU-97,,SIG)) 23260 13 6 Q0 value (ratio of resonance integral to thermal 23260 13 7 neutron activation cross-section) 23260 13 8 SAMPLE - Provider - Alfa Aesar 23260 13 9 Matrix - Foil,Pt Alloy 23260 13 10 Elemental content, % weight - 4.6 23260 13 11 Average sample thickness h,mm - 0.05 23260 13 12 - Provider - Alfa Aesar 23260 13 13 Matrix - Liquid on paper 23260 13 14 Elemental content, % weight - 0.1 23260 13 15 Average sample thickness h,mm - 1.25 23260 13 16 DECAY-DATA (44-RU-97,2.9D,DG,215.7,0.856,DG,324.5,0.1079) 23260 13 17 METHOD Measurements at channels: 23260 13 18 1 S84 23260 13 19 2 Y4 . 23260 13 20 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 13 21 recommended Er value from references - 776. eV (+-16%).23260 13 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 13 23 Uncertainty in the Q0 determination for for the simple 23260 13 24 case of one determination in one irradiation channel 23260 13 25 with one standard, given no type-B uncertainties 23260 13 26 contributions from the FCd = 1 and neutron 23260 13 27 self-shielding effects is on average 23260 13 28 2.5 % for foils, 2.6 % for compounds; 23260 13 29 include contributions from : 23260 13 30 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 13 31 for liquids/compounds in the parameter OMEGACd . 23260 13 32 - A combined type-B uncertainty from the comparator Qa 23260 13 33 factor for channels S84 - 1.8 % . 23260 13 34 - A combined type-B uncertainty of 1.2 % during 23260 13 35 Qa -> Q0 conversion, due to the uncertainty on a and 23260 13 36 an average 7 % uncertainty on the recommended effective23260 13 37 resonance energy factor for the analyte, taken from 23260 13 38 references. 23260 13 39 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 13 40 (COREL,23260013) Average Q0 . 23260 13 41 ENDBIB 39 0 23260 13 42 COMMON 2 3 23260 13 43 EN-MIN-NM EN-MEAN-DN 23260 13 44 EV EV 23260 13 45 0.5 0.0253 23260 13 46 ENDCOMMON 3 0 23260 13 47 DATA 4 1 23260 13 48 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 13 49 NO-DIM PER-CENT NO-DIM PER-CENT 23260 13 50 26.3 2. 25.3 2. 23260 13 51 ENDDATA 3 0 23260 13 52 ENDSUBENT 51 0 23260 1399999 SUBENT 23260014 20141210 224123260 14 1 BIB 10 55 23260 14 2 REACTION 1((44-RU-102(N,G)44-RU-103,,RI)// 23260 14 3 (44-RU-102(N,G)44-RU-103,,SIG)) 23260 14 4 2((44-RU-102(N,G)44-RU-103,,RI)// 23260 14 5 (44-RU-102(N,G)44-RU-103,,SIG)) 23260 14 6 Q0 value (ratio of resonance integral to thermal 23260 14 7 neutron activation cross-section) 23260 14 8 SAMPLE - Provider - Alfa Aesar 23260 14 9 Matrix - Foil,Pt Alloy 23260 14 10 Elemental content, % weight - 4.6 23260 14 11 Average sample thickness h,mm - 0.05 23260 14 12 - Provider - Alfa Aesar 23260 14 13 Matrix - Liquid on paper 23260 14 14 Elemental content, % weight - 0.1 23260 14 15 Average sample thickness h,mm - 1.25 23260 14 16 DECAY-DATA (44-RU-103,39.35D,DG,497.1,0.910,DG,610.3,0.0576) 23260 14 17 METHOD Measurements at channels: 23260 14 18 S84 23260 14 19 Y4 . 23260 14 20 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 14 21 approaches: 23260 14 22 1- the classical method: from the mean (AVG) and 23260 14 23 observed SD of the results from all channels employed, 23260 14 24 when inputting the recommended Er value from 23260 14 25 references - 181. eV (+-4%). 23260 14 26 2- the a-vector method applied on up to 3 irradiation 23260 14 27 channels: leading to simultaneous Q0 (or s0) and Er 23260 14 28 determination. 23260 14 29 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 14 30 method. 23260 14 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 14 32 Uncertainty in the Q0 determination for for the simple 23260 14 33 case of one determination in one irradiation channel 23260 14 34 with one standard, given no type-B uncertainties 23260 14 35 contributions from the FCd = 1 and neutron 23260 14 36 self-shielding effects is on average 23260 14 37 2.5 % for foils, 2.6 % for compounds; 23260 14 38 include contributions from : 23260 14 39 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 14 40 for liquids/compounds in the parameter OMEGACd . 23260 14 41 - A combined type-B uncertainty from the comparator Qa 23260 14 42 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 14 43 - A combined type-B uncertainty of 1.2 % during 23260 14 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 14 45 an average 7 % uncertainty on the recommended effective23260 14 46 resonance energy factor for the analyte, taken from 23260 14 47 references. 23260 14 48 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 14 49 E-gamma,keV k0, no-dim. 23260 14 50 497.1 7.36E-3 (+-1.2%) 23260 14 51 610.3 4.67E-4 (+-1.4%) 23260 14 52 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 14 53 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 14 54 (DEP,23260016) Measurements at two channels. 23260 14 55 COMMENT Of compiler. DATA 1 uncertainty in Table 5 of 23260 14 56 J,JRN,302,655,2014 is 6.% ( probably misprint ?). 23260 14 57 ENDBIB 55 0 23260 14 58 COMMON 2 3 23260 14 59 EN-MIN-NM EN-MEAN-DN 23260 14 60 EV EV 23260 14 61 0.5 0.0253 23260 14 62 ENDCOMMON 3 0 23260 14 63 DATA 6 1 23260 14 64 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 14 65 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 14 66 3.35 3. 3.60 2. 1556. 25. 23260 14 67 ENDDATA 3 0 23260 14 68 ENDSUBENT 67 0 23260 1499999 SUBENT 23260015 20141210 224123260 15 1 BIB 7 40 23260 15 2 REACTION 1((44-RU-102(N,G)44-RU-103,,RI)// 23260 15 3 (44-RU-102(N,G)44-RU-103,,SIG)) 23260 15 4 2((44-RU-102(N,G)44-RU-103,,RI)// 23260 15 5 (44-RU-102(N,G)44-RU-103,,SIG)) 23260 15 6 Q0 value (ratio of resonance integral to thermal 23260 15 7 neutron activation cross-section) 23260 15 8 SAMPLE - Provider - Alfa Aesar 23260 15 9 Matrix - Foil,Pt Alloy 23260 15 10 Elemental content, % weight - 4.6 23260 15 11 Average sample thickness h,mm - 0.05 23260 15 12 - Provider - Alfa Aesar 23260 15 13 Matrix - Liquid on paper 23260 15 14 Elemental content, % weight - 0.1 23260 15 15 Average sample thickness h,mm - 1.25 23260 15 16 DECAY-DATA (44-RU-103,39.35D,DG,497.1,0.910,DG,610.3,0.0576) 23260 15 17 METHOD Measurements at channels: 23260 15 18 1 S84 23260 15 19 2 Y4 . 23260 15 20 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 15 21 recommended Er value from references - 181. eV (+-4%). 23260 15 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 15 23 Uncertainty in the Q0 determination for for the simple 23260 15 24 case of one determination in one irradiation channel 23260 15 25 with one standard, given no type-B uncertainties 23260 15 26 contributions from the FCd = 1 and neutron 23260 15 27 self-shielding effects is on average 23260 15 28 2.5 % for foils, 2.6 % for compounds; 23260 15 29 include contributions from : 23260 15 30 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 15 31 for liquids/compounds in the parameter OMEGACd . 23260 15 32 - A combined type-B uncertainty from the comparator Qa 23260 15 33 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 15 34 S84 - 1.8 % . 23260 15 35 - A combined type-B uncertainty of 1.2 % during 23260 15 36 Qa -> Q0 conversion, due to the uncertainty on a and 23260 15 37 an average 7 % uncertainty on the recommended effective23260 15 38 resonance energy factor for the analyte, taken from 23260 15 39 references. 23260 15 40 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 15 41 (COREL,23260015) Average Q0 . 23260 15 42 ENDBIB 40 0 23260 15 43 COMMON 2 3 23260 15 44 EN-MIN-NM EN-MEAN-DN 23260 15 45 EV EV 23260 15 46 0.5 0.0253 23260 15 47 ENDCOMMON 3 0 23260 15 48 DATA 4 1 23260 15 49 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 15 50 NO-DIM PER-CENT NO-DIM PER-CENT 23260 15 51 3.62 2. 3.20 3. 23260 15 52 ENDDATA 3 0 23260 15 53 ENDSUBENT 52 0 23260 1599999 SUBENT 23260016 20141210 224123260 16 1 BIB 9 66 23260 16 2 REACTION 1((44-RU-104(N,G)44-RU-105,,RI)// 23260 16 3 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 16 4 2((44-RU-104(N,G)44-RU-105,,RI)// 23260 16 5 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 16 6 Q0 value (ratio of resonance integral to thermal 23260 16 7 neutron activation cross-section) 23260 16 8 SAMPLE - Provider - Alfa Aesar 23260 16 9 Matrix - Foil,Pt Alloy 23260 16 10 Elemental content, % weight - 4.6 23260 16 11 Average sample thickness h,mm - 0.05 23260 16 12 - Provider - Alfa Aesar 23260 16 13 Matrix - Liquid on paper 23260 16 14 Elemental content, % weight - 0.1 23260 16 15 Average sample thickness h,mm - 1.25 23260 16 16 DECAY-DATA (44-RU-105,4.44HR,DG,262.8,0.0657,DG,316.4,0.111, 23260 16 17 DG,469.4,0.175,DG,676.4,0.157,DG,724.3,0.473) 23260 16 18 (45-RH-105-M,42.3SEC,DG,129.6,0.200) 23260 16 19 (45-RH-105-G,35.36HR,DG,306.1,0.051,DG,318.9,0.191) 23260 16 20 METHOD Measurements at channel: 23260 16 21 S84 via Ru-105 23260 16 22 Y4 via Ru-105 23260 16 23 S84 via Rh-105-m 23260 16 24 Y4 via Rh-105-m 23260 16 25 S84 via Rh-105-g 23260 16 26 Y4 via Rh-105-g 23260 16 27 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 16 28 approaches: 23260 16 29 1- the classical method: from the mean (AVG) and 23260 16 30 observed SD of the results from all channels employed, 23260 16 31 when inputting the recommended Er value from 23260 16 32 references - 495. eV (+-10%). 23260 16 33 2- the a-vector method applied on up to 3 irradiation 23260 16 34 channels: leading to simultaneous Q0 (or s0) and Er 23260 16 35 determination. 23260 16 36 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 16 37 method. 23260 16 38 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 16 39 Uncertainty in the Q0 determination for for the simple 23260 16 40 case of one determination in one irradiation channel 23260 16 41 with one standard, given no type-B uncertainties 23260 16 42 contributions from the FCd = 1 and neutron 23260 16 43 self-shielding effects is on average 23260 16 44 2.5 % for foils, 2.6 % for compounds; 23260 16 45 include contributions from : 23260 16 46 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 16 47 for liquids/compounds in the parameter OMEGACd . 23260 16 48 - A combined type-B uncertainty from the comparator Qa 23260 16 49 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 16 50 - A combined type-B uncertainty of 1.2 % during 23260 16 51 Qa -> Q0 conversion, due to the uncertainty on a and 23260 16 52 an average 7 % uncertainty on the recommended effective23260 16 53 resonance energy factor for the analyte, taken from 23260 16 54 references. 23260 16 55 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 16 56 E-gamma,keV k0, no-dim. 23260 16 57 262.8 1.28E-4 (+-1.2%) 23260 16 58 316.4 2.17E-4 (+-1.3%) 23260 16 59 469.4 3.47E-4 (+-1.3%) 23260 16 60 676.4 3.05E-4 (+-1.3%) 23260 16 61 724.3 9.26E-4 (+-1.3%) 23260 16 62 129.6 1.03E-4 (+-1.3%) 23260 16 63 306.1 9.98E-5 (+-1.4%) 23260 16 64 318.9 3.67E-4 (+-1.4%) 23260 16 65 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 16 66 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 16 67 (DEP,23260018) Measurements at two channels. 23260 16 68 ENDBIB 66 0 23260 16 69 COMMON 2 3 23260 16 70 EN-MIN-NM EN-MEAN-DN 23260 16 71 EV EV 23260 16 72 0.5 0.0253 23260 16 73 ENDCOMMON 3 0 23260 16 74 DATA 6 1 23260 16 75 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 16 76 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 16 77 13.1 2. 13.1 2. 504. 25. 23260 16 78 ENDDATA 3 0 23260 16 79 ENDSUBENT 78 0 23260 1699999 SUBENT 23260017 20141210 224123260 17 1 BIB 7 54 23260 17 2 REACTION 1((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 3 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 4 2((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 5 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 6 3((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 7 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 8 4((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 9 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 10 5((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 11 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 12 6((44-RU-104(N,G)44-RU-105,,RI)// 23260 17 13 (44-RU-104(N,G)44-RU-105,,SIG)) 23260 17 14 Q0 value (ratio of resonance integral to thermal 23260 17 15 neutron activation cross-section) 23260 17 16 SAMPLE - Provider - Alfa Aesar 23260 17 17 Matrix - Foil,Pt Alloy 23260 17 18 Elemental content, % weight - 4.6 23260 17 19 Average sample thickness h,mm - 0.05 23260 17 20 - Provider - Alfa Aesar 23260 17 21 Matrix - Liquid on paper 23260 17 22 Elemental content, % weight - 0.1 23260 17 23 Average sample thickness h,mm - 1.25 23260 17 24 DECAY-DATA (44-RU-105,4.44HR,DG,262.8,0.0657,DG,316.4,0.111, 23260 17 25 DG,469.4,0.175,DG,676.4,0.157,DG,724.3,0.473) 23260 17 26 (45-RH-105-M,42.3SEC,DG,129.6,0.200) 23260 17 27 (45-RH-105-G,35.36HR,DG,306.1,0.051,DG,318.9,0.191) 23260 17 28 METHOD Measurements at channel: 23260 17 29 1 S84 via Ru-105 23260 17 30 2 Y4 via Ru-105 23260 17 31 3 S84 via Rh-105-m 23260 17 32 4 Y4 via Rh-105-m 23260 17 33 5 S84 via Rh-105-g 23260 17 34 6 Y4 via Rh-105-g 23260 17 35 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 17 36 recommended Er value from references - 495. eV (+-10%).23260 17 37 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 17 38 Uncertainty in the Q0 determination for for the simple 23260 17 39 case of one determination in one irradiation channel 23260 17 40 with one standard, given no type-B uncertainties 23260 17 41 contributions from the FCd = 1 and neutron 23260 17 42 self-shielding effects is on average 23260 17 43 2.5 % for foils, 2.6 % for compounds; 23260 17 44 include contributions from : 23260 17 45 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 17 46 for liquids/compounds in the parameter OMEGACd . 23260 17 47 - A combined type-B uncertainty from the comparator Qa 23260 17 48 factor for channels Y4 - 1.9 % , S84 - 1.8 % . 23260 17 49 - A combined type-B uncertainty of 1.2 % during 23260 17 50 Qa -> Q0 conversion, due to the uncertainty on a and 23260 17 51 an average 7 % uncertainty on the recommended effective23260 17 52 resonance energy factor for the analyte, taken from 23260 17 53 references. 23260 17 54 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 17 55 (COREL,23260017) Average Q0 . 23260 17 56 ENDBIB 54 0 23260 17 57 COMMON 2 3 23260 17 58 EN-MIN-NM EN-MEAN-DN 23260 17 59 EV EV 23260 17 60 0.5 0.0253 23260 17 61 ENDCOMMON 3 0 23260 17 62 DATA 12 1 23260 17 63 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 17 64 DATA 4DATA-ERR 4DATA 5DATA-ERR 5DATA 6DATA-ERR 623260 17 65 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 17 66 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 17 67 13.2 1. 13.2 2. 12.9 1. 23260 17 68 13.2 2. 12.9 1. 13.1 1. 23260 17 69 ENDDATA 6 0 23260 17 70 ENDSUBENT 69 0 23260 1799999 SUBENT 23260018 20141210 224123260 18 1 BIB 9 50 23260 18 2 REACTION ((46-PD-108(N,G)46-PD-109,,RI)// 23260 18 3 (46-PD-108(N,G)46-PD-109,,SIG)) 23260 18 4 Q0 value (ratio of resonance integral to thermal 23260 18 5 neutron activation cross-section) 23260 18 6 SAMPLE Provider - Goodfellow 23260 18 7 Matrix - Wire 23260 18 8 Elemental content, % weight > 99.99 23260 18 9 Average sample thickness h,mm - 0.5 23260 18 10 DECAY-DATA (46-PD-109-G,13.46HR,DG,311.4,0.00032,DG,602.5,0.00008,23260 18 11 DG,636.3,0.00010,DG,647.3,0.000244,DG,781.4,0.000112) 23260 18 12 (47-AG-109-M,39.6SEC,DG,88.0,0.037) 23260 18 13 METHOD Measurements at channel Y4 23260 18 14 ANALYSIS The Q0(or s0) factors were determined by 23260 18 15 - the classical method: from the mean (AVG) and 23260 18 16 observed SD of the results from all channels employed, 23260 18 17 when inputting the recommended Er value from 23260 18 18 references - 39.7eV (+-5%). 23260 18 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 18 20 Uncertainty in the Q0 determination for for the simple 23260 18 21 case of one determination in one irradiation channel 23260 18 22 with one standard, given no type-B uncertainties 23260 18 23 contributions from the FCd = 1 and neutron 23260 18 24 self-shielding effects is on average 23260 18 25 2.5 % for foils, 2.6 % for compounds; 23260 18 26 include contributions from : 23260 18 27 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 18 28 for liquids/compounds in the parameter OMEGACd . 23260 18 29 - A combined type-B uncertainty from the comparator Qa 23260 18 30 factor for channel Y4 - 1.9 % . 23260 18 31 - A combined type-B uncertainty of 1.2 % during 23260 18 32 Qa -> Q0 conversion, due to the uncertainty on a and 23260 18 33 an average 7 % uncertainty on the recommended effective23260 18 34 resonance energy factor for the analyte, taken from 23260 18 35 references. 23260 18 36 COMMENT Of compiler. 23260 18 37 - For wire - uncertainties are not specified, 23260 18 38 so compiled in free text as for foils / compounds. 23260 18 39 - DATA uncertainty in Table 5 of 23260 18 40 J,JRN,302,655,2014 is 7.% . 23260 18 41 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 18 42 E-gamma,keV k0, no-dim. 23260 18 43 311.4 1.41E-5 (+-1.8%) 23260 18 44 602.5 3.58E-6 (+-1.9%) 23260 18 45 636.3 4.52E-6 (+-1.7%) 23260 18 46 647.3 1.08E-5 (+-1.8%) 23260 18 47 781.41 4.96E-6 (+-1.7%) 23260 18 48 88.0 1.53E-3 (+-3.5%) 23260 18 49 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 18 50 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 18 51 (DEP,23260020) Two measurements used for averaging. 23260 18 52 ENDBIB 50 0 23260 18 53 COMMON 2 3 23260 18 54 EN-MIN-NM EN-MEAN-DN 23260 18 55 EV EV 23260 18 56 0.5 0.0253 23260 18 57 ENDCOMMON 3 0 23260 18 58 DATA 2 1 23260 18 59 DATA DATA-ERR 23260 18 60 NO-DIM PER-CENT 23260 18 61 26.6 4. 23260 18 62 ENDDATA 3 0 23260 18 63 ENDSUBENT 62 0 23260 1899999 SUBENT 23260019 20141210 224123260 19 1 BIB 8 40 23260 19 2 REACTION 1((46-PD-108(N,G)46-PD-109,,RI)// 23260 19 3 (46-PD-108(N,G)46-PD-109,,SIG)) 23260 19 4 2((46-PD-108(N,G)46-PD-109,,RI)// 23260 19 5 (46-PD-108(N,G)46-PD-109,,SIG)) 23260 19 6 Q0 value (ratio of resonance integral to thermal 23260 19 7 neutron activation cross-section) 23260 19 8 SAMPLE Provider - Goodfellow 23260 19 9 Matrix - Wire 23260 19 10 Elemental content, % weight > 99.99 23260 19 11 Average sample thickness h,mm - 0.5 23260 19 12 DECAY-DATA1(46-PD-109-G,13.46HR,DG,311.4,0.00032,DG,602.5,0.00008,23260 19 13 DG,636.3,0.00010,DG,647.3,0.000244,DG,781.4,0.000112) 23260 19 14 2(47-AG-109-M,39.6SEC,DG,88.0,0.037) 23260 19 15 METHOD Measurements at channel Y4 23260 19 16 1 via Pd-109 23260 19 17 2 via Ag-109-m 23260 19 18 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 19 19 recommended Er value from references - 39.7eV (+-5%). 23260 19 20 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 19 21 Uncertainty in the Q0 determination for for the simple 23260 19 22 case of one determination in one irradiation channel 23260 19 23 with one standard, given no type-B uncertainties 23260 19 24 contributions from the FCd = 1 and neutron 23260 19 25 self-shielding effects is on average 23260 19 26 2.5 % for foils, 2.6 % for compounds; 23260 19 27 include contributions from : 23260 19 28 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 19 29 for liquids/compounds in the parameter OMEGACd . 23260 19 30 - A combined type-B uncertainty from the comparator Qa 23260 19 31 factor for channel Y4 - 1.9 % . 23260 19 32 - A combined type-B uncertainty of 1.2 % during 23260 19 33 Qa -> Q0 conversion, due to the uncertainty on a and 23260 19 34 an average 7 % uncertainty on the recommended effective23260 19 35 resonance energy factor for the analyte, taken from 23260 19 36 references. 23260 19 37 COMMENT Of compiler. 23260 19 38 For wire - uncertainties are not specified, 23260 19 39 so compiled in free text as for foils / compounds. 23260 19 40 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 19 41 (COREL,23260019) Average Q0 . 23260 19 42 ENDBIB 40 0 23260 19 43 COMMON 2 3 23260 19 44 EN-MIN-NM EN-MEAN-DN 23260 19 45 EV EV 23260 19 46 0.5 0.0253 23260 19 47 ENDCOMMON 3 0 23260 19 48 DATA 4 1 23260 19 49 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 19 50 NO-DIM PER-CENT NO-DIM PER-CENT 23260 19 51 26.3 4. 26.8 4. 23260 19 52 ENDDATA 3 0 23260 19 53 ENDSUBENT 52 0 23260 1999999 SUBENT 23260020 20141210 224123260 20 1 BIB 8 44 23260 20 2 REACTION ((46-PD-110(N,G)46-PD-111-M,,RI)// 23260 20 3 (46-PD-110(N,G)46-PD-111-M,,SIG)) 23260 20 4 Q0 value (ratio of resonance integral to thermal 23260 20 5 neutron activation cross-section) 23260 20 6 SAMPLE Provider - Goodfellow 23260 20 7 Matrix - Wire 23260 20 8 Elemental content, % weight > 99.99 23260 20 9 Average sample thickness h,mm - 0.5 23260 20 10 DECAY-DATA (46-PD-111-M,5.5HR,DG,172.2,0.340) 23260 20 11 (46-PD-111-G,23.4MIN) 23260 20 12 (47-AG-111-G,7.45D,DG,245.4,0.0124,DG,342.0,0.067) 23260 20 13 ANALYSIS The Q0(or s0) factors were determined by 23260 20 14 - the classical method: from the mean (AVG) and 23260 20 15 observed SD of the results from all channels employed, 23260 20 16 when inputting the recommended Er value from 23260 20 17 references - 950.eV (+-9%). 23260 20 18 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 20 19 Uncertainty in the Q0 determination for for the simple 23260 20 20 case of one determination in one irradiation channel 23260 20 21 with one standard, given no type-B uncertainties 23260 20 22 contributions from the FCd = 1 and neutron 23260 20 23 self-shielding effects is on average 23260 20 24 2.5 % for foils, 2.6 % for compounds; 23260 20 25 include contributions from : 23260 20 26 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 20 27 for liquids/compounds in the parameter OMEGACd . 23260 20 28 - A combined type-B uncertainty from the comparator Qa 23260 20 29 factor for channel Y4 - 1.9 % . 23260 20 30 - A combined type-B uncertainty of 1.2 % during 23260 20 31 Qa -> Q0 conversion, due to the uncertainty on a and 23260 20 32 an average 7 % uncertainty on the recommended effective23260 20 33 resonance energy factor for the analyte, taken from 23260 20 34 references. 23260 20 35 COMMENT Of compiler. 23260 20 36 For wire - uncertainties are not specified, 23260 20 37 so compiled in free text as for foils / compounds. 23260 20 38 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 20 39 E-gamma,keV k0, no-dim. 23260 20 40 172.2 1.02E-5 (+-2.3%) 23260 20 41 245.4 7.86E-6 (+-2.6%) 23260 20 42 342.0 4.74E-5 (+-2.0%) 23260 20 43 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 20 44 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 20 45 (DEP,23260022) Two measurements used for averaging. 23260 20 46 ENDBIB 44 0 23260 20 47 COMMON 2 3 23260 20 48 EN-MIN-NM EN-MEAN-DN 23260 20 49 EV EV 23260 20 50 0.5 0.0253 23260 20 51 ENDCOMMON 3 0 23260 20 52 DATA 2 1 23260 20 53 DATA DATA-ERR 23260 20 54 NO-DIM PER-CENT 23260 20 55 11.9 5. 23260 20 56 ENDDATA 3 0 23260 20 57 ENDSUBENT 56 0 23260 2099999 SUBENT 23260021 20141210 224123260 21 1 BIB 8 40 23260 21 2 REACTION 1((46-PD-110(N,G)46-PD-111-M,,RI)// 23260 21 3 (46-PD-110(N,G)46-PD-111-M,,SIG)) 23260 21 4 2((46-PD-110(N,G)46-PD-111-M,,RI)// 23260 21 5 (46-PD-110(N,G)46-PD-111-M,,SIG)) 23260 21 6 Q0 value (ratio of resonance integral to thermal 23260 21 7 neutron activation cross-section) 23260 21 8 SAMPLE Provider - Goodfellow 23260 21 9 Matrix - Wire 23260 21 10 Elemental content, % weight > 99.99 23260 21 11 Average sample thickness h,mm - 0.5 23260 21 12 DECAY-DATA1(46-PD-111-M,5.5HR,DG,172.2,0.340) 23260 21 13 (46-PD-111-G,23.4MIN) 23260 21 14 2(47-AG-111-G,7.45D,DG,245.4,0.0124,DG,342.0,0.067) 23260 21 15 METHOD Measurement at channel Y4 23260 21 16 1 via Pd-11-M 23260 21 17 2 via Ag-111 23260 21 18 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 21 19 recommended Er value from references - 950.eV (+-9%). 23260 21 20 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 21 21 Uncertainty in the Q0 determination for for the simple 23260 21 22 case of one determination in one irradiation channel 23260 21 23 with one standard, given no type-B uncertainties 23260 21 24 contributions from the FCd = 1 and neutron 23260 21 25 self-shielding effects is on average 23260 21 26 2.5 % for foils, 2.6 % for compounds; 23260 21 27 include contributions from : 23260 21 28 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 21 29 for liquids/compounds in the parameter OMEGACd . 23260 21 30 - A combined type-B uncertainty from the comparator Qa 23260 21 31 factor for channel Y4 - 1.9 % . 23260 21 32 - A combined type-B uncertainty of 1.2 % during 23260 21 33 Qa -> Q0 conversion, due to the uncertainty on a and 23260 21 34 an average 7 % uncertainty on the recommended effective23260 21 35 resonance energy factor for the analyte, taken from 23260 21 36 references. 23260 21 37 COMMENT Of compiler. 23260 21 38 For wire - uncertainties are not specified, 23260 21 39 so compiled in free text as for foils / compounds. 23260 21 40 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 21 41 (COREL,23260021) Average Q0 . 23260 21 42 ENDBIB 40 0 23260 21 43 COMMON 2 3 23260 21 44 EN-MIN-NM EN-MEAN-DN 23260 21 45 EV EV 23260 21 46 0.5 0.0253 23260 21 47 ENDCOMMON 3 0 23260 21 48 DATA 4 1 23260 21 49 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 21 50 NO-DIM PER-CENT NO-DIM PER-CENT 23260 21 51 11.9 3. 9.9 3. 23260 21 52 ENDDATA 3 0 23260 21 53 ENDSUBENT 52 0 23260 2199999 SUBENT 23260022 20141210 224123260 22 1 BIB 9 70 23260 22 2 REACTION 1((47-AG-109(N,G)47-AG-110-M,,RI)// 23260 22 3 (47-AG-109(N,G)47-AG-110-M,,SIG)) 23260 22 4 2((47-AG-109(N,G)47-AG-110-M,,RI)// 23260 22 5 (47-AG-109(N,G)47-AG-110-M,,SIG)) 23260 22 6 Q0 value (ratio of resonance integral to thermal 23260 22 7 neutron activation cross-section) 23260 22 8 SAMPLE Provider - IRMM 23260 22 9 Matrix - Foil,Al alloy 23260 22 10 Elemental content, % weight - 1. 23260 22 11 Average sample thickness h,mm - 0.1 23260 22 12 DECAY-DATA (47-AG-110-M,249.8D,DG,446.8,0.037,DG,620.4,0.0273, 23260 22 13 DG,657.8,0.9561,DG,677.6,0.107,DG,687.0,0.0653, 23260 22 14 DG,706.7,0.1669,DG,744.3,0.0477,DG,763.9,0.226, 23260 22 15 DG,818.0,0.0743,DG,884.7,0.750,DG,937.5,0.350, 23260 22 16 DG,1384.3,0.251,DG,1475.8,0.0408,DG,1505.0,0.1333, 23260 22 17 DG,1562.3,0.0122) 23260 22 18 METHOD Measurement at channel: 23260 22 19 S85 23260 22 20 Y4 23260 22 21 X26 23260 22 22 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 22 23 approaches: 23260 22 24 1- the classical method: from the mean (AVG) and 23260 22 25 observed SD of the results from all channels employed, 23260 22 26 when inputting the recommended Er value from 23260 22 27 references - 6.08 eV (+-1%). 23260 22 28 2- the a-vector method applied on up to 3 irradiation 23260 22 29 channels: leading to simultaneous Q0 (or s0) and Er 23260 22 30 determination. 23260 22 31 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 22 32 method. 23260 22 33 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 22 34 Uncertainty in the Q0 determination for for the simple 23260 22 35 case of one determination in one irradiation channel 23260 22 36 with one standard, given no type-B uncertainties 23260 22 37 contributions from the FCd = 1 and neutron 23260 22 38 self-shielding effects is on average 23260 22 39 2.5 % for foils, 2.6 % for compounds; 23260 22 40 include contributions from : 23260 22 41 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 22 42 for liquids/compounds in the parameter OMEGACd . 23260 22 43 - A combined type-B uncertainty from the comparator Qa 23260 22 44 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 22 45 S84 - 1.8 % . 23260 22 46 - A combined type-B uncertainty of 1.2 % during 23260 22 47 Qa -> Q0 conversion, due to the uncertainty on a and 23260 22 48 an average 7 % uncertainty on the recommended effective23260 22 49 resonance energy factor for the analyte, taken from 23260 22 50 references. 23260 22 51 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 22 52 E-gamma,keV k0, no-dim. 23260 22 53 446.8 1.37E-3 (+-2.3%) 23260 22 54 620.4 1.01E-3 (+-2.3%) 23260 22 55 657.8 3.53E-2 (+-1.8%) 23260 22 56 677.6 3.93E-3 (+-1.9%) 23260 22 57 687.0 2.43E-3 (+-1.7%) 23260 22 58 706.7 6.20E-3 (+-1.8%) 23260 22 59 744.3 1.77E-3 (+-2.1%) 23260 22 60 763.9 8.35E-3 (+-1.9%) 23260 22 61 818.0 2.73E-3 (+-2.1%) 23260 22 62 884.7 2.75E-2 (+-2.0%) 23260 22 63 937.5 1.29E-2 (+-1.7%) 23260 22 64 1384.3 9.22E-3 (+-2.6%) 23260 22 65 1475.8 1.51E-3 (+-2.0%) 23260 22 66 1505.0 4.93E-3 (+-2.3%) 23260 22 67 1562.3 4.54E-4 (+-1.8%) 23260 22 68 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 22 69 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 22 70 Table 6 of J,JRN,302,631,2014. 23260 22 71 1(DEP,23260024) Q0 measured at 3 channels. 23260 22 72 ENDBIB 70 0 23260 22 73 COMMON 2 3 23260 22 74 EN-MIN-NM EN-MEAN-DN 23260 22 75 EV EV 23260 22 76 0.5 0.0253 23260 22 77 ENDCOMMON 3 0 23260 22 78 DATA 6 1 23260 22 79 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 22 80 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 22 81 16.5 2. 16.5 2. 5.7 7. 23260 22 82 ENDDATA 3 0 23260 22 83 ENDSUBENT 82 0 23260 2299999 SUBENT 23260023 20141210 224123260 23 1 BIB 7 45 23260 23 2 REACTION 1((47-AG-109(N,G)47-AG-110-M,,RI)// 23260 23 3 (47-AG-109(N,G)47-AG-110-M,,SIG)) 23260 23 4 2((47-AG-109(N,G)47-AG-110-M,,RI)// 23260 23 5 (47-AG-109(N,G)47-AG-110-M,,SIG)) 23260 23 6 3((47-AG-109(N,G)47-AG-110-M,,RI)// 23260 23 7 (47-AG-109(N,G)47-AG-110-M,,SIG)) 23260 23 8 Q0 value (ratio of resonance integral to thermal 23260 23 9 neutron activation cross-section) 23260 23 10 SAMPLE Provider - IRMM 23260 23 11 Matrix - Foil,Al alloy 23260 23 12 Elemental content, % weight - 1. 23260 23 13 Average sample thickness h,mm - 0.1 23260 23 14 DECAY-DATA (47-AG-110-M,249.8D,DG,446.8,0.037,DG,620.4,0.0273, 23260 23 15 DG,657.8,0.9561,DG,677.6,0.107,DG,687.0,0.0653, 23260 23 16 DG,706.7,0.1669,DG,744.3,0.0477,DG,763.9,0.226, 23260 23 17 DG,818.0,0.0743,DG,884.7,0.750,DG,937.5,0.350, 23260 23 18 DG,1384.3,0.251,DG,1475.8,0.0408,DG,1505.0,0.1333, 23260 23 19 DG,1562.3,0.0122) 23260 23 20 METHOD Measurement at channel: 23260 23 21 1 S85 23260 23 22 2 Y4 23260 23 23 3 X26 23260 23 24 ANALYSIS The Q0(or s0) factors were determined inputting the 23260 23 25 recommended Er value from references - 6.08 eV (+-1%). 23260 23 26 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 23 27 Uncertainty in the Q0 determination for for the simple 23260 23 28 case of one determination in one irradiation channel 23260 23 29 with one standard, given no type-B uncertainties 23260 23 30 contributions from the FCd = 1 and neutron 23260 23 31 self-shielding effects is on average 23260 23 32 2.5 % for foils, 2.6 % for compounds; 23260 23 33 include contributions from : 23260 23 34 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 23 35 for liquids/compounds in the parameter OMEGACd . 23260 23 36 - A combined type-B uncertainty from the comparator Qa 23260 23 37 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 23 38 S84 - 1.8 % . 23260 23 39 - A combined type-B uncertainty of 1.2 % during 23260 23 40 Qa -> Q0 conversion, due to the uncertainty on a and 23260 23 41 an average 7 % uncertainty on the recommended effective23260 23 42 resonance energy factor for the analyte, taken from 23260 23 43 references. 23260 23 44 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 23 45 Table 6 of J,JRN,302,631,2014. 23260 23 46 (COREL,23260025) Average Q0 . 23260 23 47 ENDBIB 45 0 23260 23 48 COMMON 2 3 23260 23 49 EN-MIN-NM EN-MEAN-DN 23260 23 50 EV EV 23260 23 51 0.5 0.0253 23260 23 52 ENDCOMMON 3 0 23260 23 53 DATA 6 1 23260 23 54 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 23 55 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 23 56 16.3 2. 16.7 1. 16.3 1. 23260 23 57 ENDDATA 3 0 23260 23 58 ENDSUBENT 57 0 23260 2399999 SUBENT 23260024 20141210 224123260 24 1 BIB 9 58 23260 24 2 REACTION 1((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 24 3 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 24 4 2((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 24 5 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 24 6 Q0 value (ratio of resonance integral to thermal 23260 24 7 neutron activation cross-section) 23260 24 8 SAMPLE Provider - NIST 23260 24 9 Matrix - Liquid on paper 23260 24 10 Elemental content, % weight - 1. 23260 24 11 Average sample thickness h,mm - 1.25 23260 24 12 DECAY-DATA (48-CD-115-G,53.5HR,DG,527.9,0.275) 23260 24 13 (49-IN-115-M,4.486HR,DG,336.2,0.458) 23260 24 14 METHOD Measurement at channel: 23260 24 15 S85, via Cd-115. 23260 24 16 Y4, via Cd-115. 23260 24 17 X26, via Cd-115. 23260 24 18 S85, via In-115-M. 23260 24 19 Y4, via In-115-M. 23260 24 20 X26, via In-115-M. 23260 24 21 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 24 22 approaches: 23260 24 23 1- the classical method: from the mean (AVG) and 23260 24 24 observed SD of the results from all channels employed, 23260 24 25 when inputting the recommended Er value from 23260 24 26 references - 207. eV (+-19%). 23260 24 27 2- the a-vector method applied on up to 3 irradiation 23260 24 28 channels: leading to simultaneous Q0 (or s0) and Er 23260 24 29 determination. 23260 24 30 The Cd transmission factor FCd (a parameter that 23260 24 31 accounts for a possible loss in the induced activity of23260 24 32 samples irradiated inside a Cd-cover, dimensionless) 23260 24 33 0.40 . 23260 24 34 MISC-COL (MISC) Effective resonance energy defined by a-vector 23260 24 35 method. 23260 24 36 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 24 37 Uncertainty in the Q0 determination for for the simple 23260 24 38 case of one determination in one irradiation channel 23260 24 39 with one standard include contributions from : 23260 24 40 - For an isotope 114Cd maximum 5 % uncertainty in 23260 24 41 the observed FCd = 0.40, meaning a 5.2 % combined 23260 24 42 uncertainty for this isotope OMEGACd factor (liquid 23260 24 43 standard). 23260 24 44 - A combined type-B uncertainty from the comparator Qa 23260 24 45 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 24 46 S84 - 1.8 % . 23260 24 47 - A combined type-B uncertainty of 1.2 % during 23260 24 48 Qa -> Q0 conversion, due to the uncertainty on a and 23260 24 49 an average 7 % uncertainty on the recommended effective23260 24 50 resonance energy factor for the analyte, taken from 23260 24 51 references. 23260 24 52 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 24 53 E-gamma,keV k0, no-dim. 23260 24 54 527.9 4.97E-4 (+-5.0%) 23260 24 55 336.2 8.07E-4 (+-5.0%) 23260 24 56 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 24 57 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 24 58 Table 6 of J,JRN,302,631,2014. 23260 24 59 1(DEP,23260026) Q0 measured at different channels. 23260 24 60 ENDBIB 58 0 23260 24 61 COMMON 2 3 23260 24 62 EN-MIN-NM EN-MEAN-DN 23260 24 63 EV EV 23260 24 64 0.5 0.0253 23260 24 65 ENDCOMMON 3 0 23260 24 66 DATA 6 1 23260 24 67 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 24 68 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 24 69 31.4 4. 31.0 4. 202. 33. 23260 24 70 ENDDATA 3 0 23260 24 71 ENDSUBENT 70 0 23260 2499999 SUBENT 23260025 20141210 224123260 25 1 BIB 7 54 23260 25 2 REACTION 1((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 3 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 4 2((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 5 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 6 3((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 7 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 8 4((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 9 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 10 5((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 11 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 12 6((48-CD-114(N,G)48-CD-115-G,,RI)// 23260 25 13 (48-CD-114(N,G)48-CD-115-G,,SIG)) 23260 25 14 Q0 value (ratio of resonance integral to thermal 23260 25 15 neutron activation cross-section) 23260 25 16 SAMPLE Provider - NIST 23260 25 17 Matrix - Liquid on paper 23260 25 18 Elemental content, % weight - 1. 23260 25 19 Average sample thickness h,mm - 1.25 23260 25 20 DECAY-DATA (48-CD-115-G,53.5HR,DG,527.9,0.275) 23260 25 21 (49-IN-115-M,4.486HR,DG,336.2,0.458) 23260 25 22 METHOD Measurement at channel: 23260 25 23 1 S85, via Cd-115. 23260 25 24 2 Y4, via Cd-115. 23260 25 25 3 X26, via Cd-115. 23260 25 26 4 S85, via In-115-M. 23260 25 27 5 Y4, via In-115-M. 23260 25 28 6 X26, via In-115-M. 23260 25 29 The Cd transmission factor FCd (a parameter that 23260 25 30 accounts for a possible loss in the induced activity of23260 25 31 samples irradiated inside a Cd-cover, dimensionless) 23260 25 32 0.40 . 23260 25 33 ANALYSIS The Q0(or s0) factors were determined 23260 25 34 inputting the recommended Er value from 23260 25 35 references - 6.08 eV (+-1%). 23260 25 36 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 25 37 Uncertainty in the Q0 determination for for the simple 23260 25 38 case of one determination in one irradiation channel 23260 25 39 with one standard include contributions from : 23260 25 40 - For an isotope 114Cd maximum 5 % uncertainty in 23260 25 41 the observed FCd = 0.40, meaning a 5.2 % combined 23260 25 42 uncertainty for this isotope OMEGACd factor (liquid 23260 25 43 standard). 23260 25 44 - A combined type-B uncertainty from the comparator Qa 23260 25 45 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 25 46 S84 - 1.8 % . 23260 25 47 - A combined type-B uncertainty of 1.2 % during 23260 25 48 Qa -> Q0 conversion, due to the uncertainty on a and 23260 25 49 an average 7 % uncertainty on the recommended effective23260 25 50 resonance energy factor for the analyte, taken from 23260 25 51 references. 23260 25 52 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 25 53 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 25 54 Table 6 of J,JRN,302,631,2014. 23260 25 55 (COREL,23260025) Average Q0 . 23260 25 56 ENDBIB 54 0 23260 25 57 COMMON 2 3 23260 25 58 EN-MIN-NM EN-MEAN-DN 23260 25 59 EV EV 23260 25 60 0.5 0.0253 23260 25 61 ENDCOMMON 3 0 23260 25 62 DATA 12 1 23260 25 63 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 25 64 DATA 4DATA-ERR 4DATA 5DATA-ERR 5DATA 6DATA-ERR 623260 25 65 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 25 66 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 25 67 31.8 7. 30.3 5. 32.5 4. 23260 25 68 32.3 7. 30.4 5. 33.1 4. 23260 25 69 ENDDATA 6 0 23260 25 70 ENDSUBENT 69 0 23260 2599999 SUBENT 23260026 20141210 224123260 26 1 BIB 9 57 23260 26 2 REACTION 1((49-IN-113(N,G)49-IN-114-M,,RI)// 23260 26 3 (49-IN-113(N,G)49-IN-114-M,,SIG)) 23260 26 4 2((49-IN-113(N,G)49-IN-114-M,,RI)// 23260 26 5 (49-IN-113(N,G)49-IN-114-M,,SIG)) 23260 26 6 Q0 value (ratio of resonance integral to thermal 23260 26 7 neutron activation cross-section) 23260 26 8 SAMPLE Provider - IRMM 23260 26 9 Average sample thickness h,mm - 0.1 23260 26 10 -Matrix - Foil, Sn alloy 23260 26 11 Elemental content, % weight - 15.4 23260 26 12 -Matrix - Foil, Sn alloy 23260 26 13 Elemental content, % weight - 5.15 23260 26 14 -Matrix - Foil, Al alloy 23260 26 15 Elemental content, % weight - 1. 23260 26 16 -Matrix - Foil, Al alloy 23260 26 17 Elemental content, % weight - 0.017 23260 26 18 DECAY-DATA (49-IN-114-M,49.51D,DG,190.3,0.1556,DG,558.4,0.0439, 23260 26 19 DG,725.2,0.0439) 23260 26 20 METHOD Measurement at channels: 23260 26 21 Y4 23260 26 22 X26 23260 26 23 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 26 24 approaches: 23260 26 25 1- the classical method: from the mean (AVG) and 23260 26 26 observed SD of the results from all channels employed, 23260 26 27 when inputting the recommended Er value from 23260 26 28 references - 6.41 eV (+-15%). 23260 26 29 2- the a-vector method applied on up to 3 irradiation 23260 26 30 channels: leading to simultaneous Q0 (or s0) and Er 23260 26 31 determination. 23260 26 32 MISC-COL (MISC) Effective resonance energy Er defined by 23260 26 33 a-vector method. 23260 26 34 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 26 35 Uncertainty in the Q0 determination for for the simple 23260 26 36 case of one determination in one irradiation channel 23260 26 37 with one standard, given no type-B uncertainties 23260 26 38 contributions from the FCd = 1 and neutron 23260 26 39 self-shielding effects is on average 23260 26 40 2.5 % for foils, 2.6 % for compounds; 23260 26 41 include contributions from : 23260 26 42 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 26 43 for liquids/compounds in the parameter OMEGACd . 23260 26 44 - A combined type-B uncertainty from the comparator Qa 23260 26 45 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 26 46 - A combined type-B uncertainty of 1.2 % during 23260 26 47 Qa -> Q0 conversion, due to the uncertainty on a and 23260 26 48 an average 7 % uncertainty on the recommended effective23260 26 49 resonance energy factor for the analyte, taken from 23260 26 50 references. 23260 26 51 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 26 52 E-gamma,keV k0, no-dim. 23260 26 53 190.3 1.02E-3 (+-1.3%) 23260 26 54 558.4 2.70E-4 (+-1.2%) 23260 26 55 725.2 2.79E-4 (+-1.2%) 23260 26 56 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 26 57 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 26 58 1(DEP,23260028) Q0 measured at different channels. 23260 26 59 ENDBIB 57 0 23260 26 60 COMMON 2 3 23260 26 61 EN-MIN-NM EN-MEAN-DN 23260 26 62 EV EV 23260 26 63 0.5 0.0253 23260 26 64 ENDCOMMON 3 0 23260 26 65 DATA 6 1 23260 26 66 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 26 67 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 26 68 24.1 2. 23.7 2. 4.99 25. 23260 26 69 ENDDATA 3 0 23260 26 70 ENDSUBENT 69 0 23260 2699999 SUBENT 23260027 20141210 224123260 27 1 BIB 7 42 23260 27 2 REACTION 1((49-IN-113(N,G)49-IN-114-M,,RI)// 23260 27 3 (49-IN-113(N,G)49-IN-114-M,,SIG)) 23260 27 4 2((49-IN-113(N,G)49-IN-114-M,,RI)// 23260 27 5 (49-IN-113(N,G)49-IN-114-M,,SIG)) 23260 27 6 Q0 value (ratio of resonance integral to thermal 23260 27 7 neutron activation cross-section) 23260 27 8 SAMPLE Provider - IRMM 23260 27 9 Average sample thickness h,mm - 0.1 23260 27 10 -Matrix - Foil, Sn alloy 23260 27 11 Elemental content, % weight - 15.4 23260 27 12 -Matrix - Foil, Sn alloy 23260 27 13 Elemental content, % weight - 5.15 23260 27 14 -Matrix - Foil, Al alloy 23260 27 15 Elemental content, % weight - 1. 23260 27 16 -Matrix - Foil, Al alloy 23260 27 17 Elemental content, % weight - 0.017 23260 27 18 DECAY-DATA (49-IN-114-M,49.51D,DG,190.3,0.1556,DG,558.4,0.0439, 23260 27 19 DG,725.2,0.0439) 23260 27 20 METHOD Measurement at channels: 23260 27 21 1 Y4 23260 27 22 2 X26 23260 27 23 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 27 24 recommended Er value from references - 6.41 eV (+-15%).23260 27 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 27 26 Uncertainty in the Q0 determination for for the simple 23260 27 27 case of one determination in one irradiation channel 23260 27 28 with one standard, given no type-B uncertainties 23260 27 29 contributions from the FCd = 1 and neutron 23260 27 30 self-shielding effects is on average 23260 27 31 2.5 % for foils, 2.6 % for compounds; 23260 27 32 include contributions from : 23260 27 33 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 27 34 for liquids/compounds in the parameter OMEGACd . 23260 27 35 - A combined type-B uncertainty from the comparator Qa 23260 27 36 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 27 37 - A combined type-B uncertainty of 1.2 % during 23260 27 38 Qa -> Q0 conversion, due to the uncertainty on a and 23260 27 39 an average 7 % uncertainty on the recommended effective23260 27 40 resonance energy factor for the analyte, taken from 23260 27 41 references. 23260 27 42 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 27 43 (COREL,23260027) Average Q0 . 23260 27 44 ENDBIB 42 0 23260 27 45 COMMON 2 3 23260 27 46 EN-MIN-NM EN-MEAN-DN 23260 27 47 EV EV 23260 27 48 0.5 0.0253 23260 27 49 ENDCOMMON 3 0 23260 27 50 DATA 4 1 23260 27 51 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 27 52 NO-DIM PER-CENT NO-DIM PER-CENT 23260 27 53 24.0 3. 24.2 2. 23260 27 54 ENDDATA 3 0 23260 27 55 ENDSUBENT 54 0 23260 2799999 SUBENT 23260028 20141210 224123260 28 1 BIB 10 60 23260 28 2 REACTION ((49-IN-115(N,G)49-IN-116-M,,RI)// 23260 28 3 (49-IN-115(N,G)49-IN-116-M,,SIG)) 23260 28 4 Q0 value (ratio of resonance integral to thermal 23260 28 5 neutron activation cross-section) 23260 28 6 SAMPLE Provider - IRMM 23260 28 7 Average sample thickness h,mm - 0.1 23260 28 8 -Matrix - Foil, Sn alloy 23260 28 9 Elemental content, % weight - 15.4 23260 28 10 -Matrix - Foil, Sn alloy 23260 28 11 Elemental content, % weight - 5.15 23260 28 12 -Matrix - Foil, Al alloy 23260 28 13 Elemental content, % weight - 1. 23260 28 14 -Matrix - Foil, Al alloy 23260 28 15 Elemental content, % weight - 0.017 23260 28 16 DECAY-DATA (49-IN-116-M1,54.41MIN,DG,138.3,0.037,DG,416.9,0.272, 23260 28 17 DG,818.7,0.1213,DG,1097.3,0.585,DG,1293.5,0.848, 23260 28 18 DG,1507.4,0.0992,DG,2112.1,0.1509) 23260 28 19 METHOD Measurement at S84 channel. 23260 28 20 REL-REF (R,,F.De Corte,T,DE CORTE,1987) 23260 28 21 The k0-standardization method: a move to the 23260 28 22 optimization of neutron activation analysis. 23260 28 23 Ph.D. Thesis. Gent Universiteit, Belgium. 23260 28 24 ANALYSIS FCd=0.927 value adopted from REL-REF of F.De Corte. 23260 28 25 The Q0(or s0) factors were determined by 23260 28 26 the classical method: from the mean (AVG) and 23260 28 27 observed SD of the results from all channels employed, 23260 28 28 when inputting the recommended Er value from 23260 28 29 references - 1.56 eV (+-7%). 23260 28 30 ERR-ANALYS (DATA-ERR1) One sigma uncertainty (Table 5). 23260 28 31 (DATA-ERR2) Standard deviation ( from Suppl.material- 23260 28 32 direct measurement). 23260 28 33 Uncertainty in the Q0 determination for for the simple 23260 28 34 case of one determination in one irradiation channel 23260 28 35 with one standard, given no type-B uncertainties 23260 28 36 contributions from the FCd = 1 and neutron 23260 28 37 self-shielding effects is on average 23260 28 38 2.5 % for foils, 2.6 % for compounds; 23260 28 39 include contributions from : 23260 28 40 - The combined uncertainty of 1.5 % for In-115 23260 28 41 in the parameter OMEGACd . 23260 28 42 - A combined type-B uncertainty from the comparator Qa 23260 28 43 factor for channels S84 - 1.8 % . 23260 28 44 - A combined type-B uncertainty of 1.2 % during 23260 28 45 Qa -> Q0 conversion, due to the uncertainty on a and 23260 28 46 an average 7 % uncertainty on the recommended effective23260 28 47 resonance energy factor for the analyte, taken from 23260 28 48 references. 23260 28 49 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 28 50 E-gamma,keV k0, no-dim. 23260 28 51 138.3 1.02E-3 (+-1.4%) 23260 28 52 416.9 7.59E-1 (+-1.6%) 23260 28 53 818.7 3.39E-1 (+-1.8%) 23260 28 54 1097.3 1.60E+0 (+-1.4%) 23260 28 55 1293.5 2.32E+0 (+-1.5%) 23260 28 56 1507.4 2.70E-1 (+-1.4%) 23260 28 57 2112.1 4.15E-1 (+-1.6%) 23260 28 58 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 28 59 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 28 60 COMMENT Of compiler. DATA uncertainty in Table 5 of 23260 28 61 J,JRN,302,655,2014 is 3.%. 23260 28 62 ENDBIB 60 0 23260 28 63 COMMON 2 3 23260 28 64 EN-MIN-NM EN-MEAN-DN 23260 28 65 EV EV 23260 28 66 0.5 0.0253 23260 28 67 ENDCOMMON 3 0 23260 28 68 DATA 3 1 23260 28 69 DATA DATA-ERR1 DATA-ERR2 23260 28 70 NO-DIM PER-CENT PER-CENT 23260 28 71 16.7 3. 2. 23260 28 72 ENDDATA 3 0 23260 28 73 ENDSUBENT 72 0 23260 2899999 SUBENT 23260029 20151013 224523260 29 1 BIB 10 55 23260 29 2 REACTION 1((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 29 3 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 29 4 2((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 29 5 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 29 6 Q0 value (ratio of resonance integral to thermal 23260 29 7 neutron activation cross-section) 23260 29 8 SAMPLE Provider - IRMM 23260 29 9 Average sample thickness h,mm - 0.1 23260 29 10 Matrix - Foil, In alloy 23260 29 11 - Elemental content, % weight - 84.6 23260 29 12 - Elemental content, % weight - 94.85 23260 29 13 DECAY-DATA (50-SN-113-G,115.1D,DG,255.1,0.0211) 23260 29 14 (49-IN-113-M,99.48MIN,DG,391.7,0.6497) 23260 29 15 METHOD Measurement at channels: 23260 29 16 Y4 via Sn-113 23260 29 17 X26 via Sn-113 23260 29 18 Y4 via In-113-m 23260 29 19 X26 via In-113-m 23260 29 20 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 29 21 approaches: 23260 29 22 1- the classical method: from the mean (AVG) and 23260 29 23 observed SD of the results from all channels employed, 23260 29 24 when inputting the recommended Er value from 23260 29 25 references - 107. eV (+-3%). 23260 29 26 2- the a-vector method applied on up to 3 irradiation 23260 29 27 channels: leading to simultaneous Q0 (or s0) and Er 23260 29 28 determination. 23260 29 29 MISC-COL (MISC) Effective resonance energy Er defined by 23260 29 30 a-vector method. 23260 29 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 29 32 Uncertainty in the Q0 determination for the simple 23260 29 33 case of one determination in one irradiation channel 23260 29 34 with one standard, given no type-B uncertainties 23260 29 35 contributions from the factor Cd (F(Cd))=1 and neutron 23260 29 36 self-shielding effects is on average 23260 29 37 2.5 % for foils, 2.6 % for compounds; 23260 29 38 include contributions from : 23260 29 39 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 29 40 for liquids/compounds in the parameter OMEGACd . 23260 29 41 - A combined type-B uncertainty from the comparator Qa 23260 29 42 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 29 43 - A combined type-B uncertainty of 1.2 % during 23260 29 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 29 45 an average 7 % uncertainty on the recommended effective23260 29 46 resonance energy factor for the analyte, taken from 23260 29 47 references. 23260 29 48 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 29 49 E-gamma,keV k0, no-dim. 23260 29 50 255.1 1.95E-6 (+-1.2%) 23260 29 51 391.7 5.99E-5 (+-1.2%) 23260 29 52 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 29 53 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 29 54 1(DEP,23260030) Q0 measured at different channels. 23260 29 55 HISTORY (20151013A) SD: SF4=Sn-113->Sn-113g, SF5=M+ (IT=91%) in23260 29 56 REACTION code following N.Otsuka's remark. 23260 29 57 ENDBIB 55 0 23260 29 58 COMMON 2 3 23260 29 59 EN-MIN-NM EN-MEAN-DN 23260 29 60 EV EV 23260 29 61 0.5 0.0253 23260 29 62 ENDCOMMON 3 0 23260 29 63 DATA 6 1 23260 29 64 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 29 65 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 29 66 48.3 4. 45.2 4. 49.9 25. 23260 29 67 ENDDATA 3 0 23260 29 68 ENDSUBENT 67 0 23260 2999999 SUBENT 23260030 20151013 224523260 30 1 BIB 8 45 23260 30 2 REACTION 1((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 30 3 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 30 4 2((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 30 5 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 30 6 3((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 30 7 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 30 8 4((50-SN-112(N,G)50-SN-113-G,M+,RI)// 23260 30 9 (50-SN-112(N,G)50-SN-113-G,M+,SIG)) 23260 30 10 Q0 value (ratio of resonance integral to thermal 23260 30 11 neutron activation cross-section) 23260 30 12 SAMPLE Provider - IRMM 23260 30 13 Average sample thickness h,mm - 0.1 23260 30 14 Matrix - Foil, In alloy 23260 30 15 - Elemental content, % weight - 84.6 23260 30 16 - Elemental content, % weight - 94.85 23260 30 17 DECAY-DATA (50-SN-113-G,115.1D,DG,255.1,0.0211) 23260 30 18 (49-IN-113-M,99.48MIN,DG,391.7,0.6497) 23260 30 19 METHOD Measurement at channels: 23260 30 20 1 Y4 via Sn-113 23260 30 21 2 X26 via Sn-113 23260 30 22 3 Y4 via In-113-m 23260 30 23 4 X26 via In-113-m 23260 30 24 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 30 25 recommended Er value from references - 107. eV (+-3%). 23260 30 26 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 30 27 Uncertainty in the Q0 determination for the simple 23260 30 28 case of one determination in one irradiation channel 23260 30 29 with one standard, given no type-B uncertainties 23260 30 30 contributions from the FCd = 1 and neutron 23260 30 31 self-shielding effects is on average 23260 30 32 2.5 % for foils, 2.6 % for compounds; 23260 30 33 include contributions from : 23260 30 34 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 30 35 for liquids/compounds in the parameter OMEGACd . 23260 30 36 - A combined type-B uncertainty from the comparator Qa 23260 30 37 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 30 38 - A combined type-B uncertainty of 1.2 % during 23260 30 39 Qa -> Q0 conversion, due to the uncertainty on a and 23260 30 40 an average 7 % uncertainty on the recommended effective23260 30 41 resonance energy factor for the analyte, taken from 23260 30 42 references. 23260 30 43 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 30 44 HISTORY (20151013A) SD: SF4=Sn-113->Sn-113g, SF5=M+ (IT=91%) in23260 30 45 REACTION code following N.Otsuka's remark. STATUS 23260 30 46 'COREL' deleted. 23260 30 47 ENDBIB 45 0 23260 30 48 COMMON 2 3 23260 30 49 EN-MIN-NM EN-MEAN-DN 23260 30 50 EV EV 23260 30 51 0.5 0.0253 23260 30 52 ENDCOMMON 3 0 23260 30 53 DATA 8 1 23260 30 54 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 30 55 DATA 4DATA-ERR 4 23260 30 56 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 30 57 NO-DIM PER-CENT 23260 30 58 47.6 2. 49.1 1. 55.8 3. 23260 30 59 55.7 3. 23260 30 60 ENDDATA 6 0 23260 30 61 ENDSUBENT 60 0 23260 3099999 SUBENT 23260031 20141210 224123260 31 1 BIB 9 50 23260 31 2 REACTION 1((50-SN-116(N,G)50-SN-117-M,,RI)// 23260 31 3 (50-SN-116(N,G)50-SN-117-M,,SIG)) 23260 31 4 2((50-SN-116(N,G)50-SN-117-M,,RI)// 23260 31 5 (50-SN-116(N,G)50-SN-117-M,,SIG)) 23260 31 6 Q0 value (ratio of resonance integral to thermal 23260 31 7 neutron activation cross-section) 23260 31 8 SAMPLE Provider - IRMM 23260 31 9 Average sample thickness h,mm - 0.1 23260 31 10 Matrix - Foil, In alloy 23260 31 11 - Elemental content, % weight - 84.6 23260 31 12 - Elemental content, % weight - 94.85 23260 31 13 DECAY-DATA (50-SN-117-M,13.6D,DG,156.0,0.02113,DG,158.4,0.864) 23260 31 14 METHOD Measurement at channels: 23260 31 15 Y4 23260 31 16 X26 23260 31 17 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 31 18 approaches: 23260 31 19 1- the classical method: from the mean (AVG) and 23260 31 20 observed SD of the results from all channels employed, 23260 31 21 when inputting the recommended Er value from 23260 31 22 references - 128. eV (+-3%). 23260 31 23 2- the a-vector method applied on up to 3 irradiation 23260 31 24 channels: leading to simultaneous Q0 (or s0) and Er 23260 31 25 determination. 23260 31 26 MISC-COL (MISC) Effective resonance energy Er defined by 23260 31 27 a-vector method. 23260 31 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 31 29 Uncertainty in the Q0 determination for for the simple 23260 31 30 case of one determination in one irradiation channel 23260 31 31 with one standard, given no type-B uncertainties 23260 31 32 contributions from the FCd = 1 and neutron 23260 31 33 self-shielding effects is on average 23260 31 34 2.5 % for foils, 2.6 % for compounds; 23260 31 35 include contributions from : 23260 31 36 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 31 37 for liquids/compounds in the parameter OMEGACd . 23260 31 38 - A combined type-B uncertainty from the comparator Qa 23260 31 39 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 31 40 - A combined type-B uncertainty of 1.2 % during 23260 31 41 Qa -> Q0 conversion, due to the uncertainty on a and 23260 31 42 an average 7 % uncertainty on the recommended effective23260 31 43 resonance energy factor for the analyte, taken from 23260 31 44 references. 23260 31 45 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 31 46 E-gamma,keV k0, no-dim. 23260 31 47 156.0 3.33E-7 (+-1.2%) 23260 31 48 158.4 1.36E-5 (+-1.2%) 23260 31 49 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 31 50 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 31 51 1(DEP,23260033) Q0 measured at different channels. 23260 31 52 ENDBIB 50 0 23260 31 53 COMMON 2 3 23260 31 54 EN-MIN-NM EN-MEAN-DN 23260 31 55 EV EV 23260 31 56 0.5 0.0253 23260 31 57 ENDCOMMON 3 0 23260 31 58 DATA 6 1 23260 31 59 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 31 60 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 31 61 55.8 3. 55.9 3. 130. 25. 23260 31 62 ENDDATA 3 0 23260 31 63 ENDSUBENT 62 0 23260 3199999 SUBENT 23260032 20141210 224123260 32 1 BIB 7 36 23260 32 2 REACTION 1((50-SN-116(N,G)50-SN-117-M,,RI)// 23260 32 3 (50-SN-116(N,G)50-SN-117-M,,SIG)) 23260 32 4 2((50-SN-116(N,G)50-SN-117-M,,RI)// 23260 32 5 (50-SN-116(N,G)50-SN-117-M,,SIG)) 23260 32 6 Q0 value (ratio of resonance integral to thermal 23260 32 7 neutron activation cross-section) 23260 32 8 SAMPLE Provider - IRMM 23260 32 9 Average sample thickness h,mm - 0.1 23260 32 10 Matrix - Foil, In alloy 23260 32 11 - Elemental content, % weight - 84.6 23260 32 12 - Elemental content, % weight - 94.85 23260 32 13 DECAY-DATA (50-SN-117-M,13.6D,DG,156.0,0.02113,DG,158.4,0.864) 23260 32 14 METHOD Measurement at channels: 23260 32 15 1 Y4 23260 32 16 2 X26 23260 32 17 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 32 18 recommended Er value from references - 128. eV (+-3%). 23260 32 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 32 20 Uncertainty in the Q0 determination for for the simple 23260 32 21 case of one determination in one irradiation channel 23260 32 22 with one standard, given no type-B uncertainties 23260 32 23 contributions from the FCd = 1 and neutron 23260 32 24 self-shielding effects is on average 23260 32 25 2.5 % for foils, 2.6 % for compounds; 23260 32 26 include contributions from : 23260 32 27 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 32 28 for liquids/compounds in the parameter OMEGACd . 23260 32 29 - A combined type-B uncertainty from the comparator Qa 23260 32 30 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 32 31 - A combined type-B uncertainty of 1.2 % during 23260 32 32 Qa -> Q0 conversion, due to the uncertainty on a and 23260 32 33 an average 7 % uncertainty on the recommended effective23260 32 34 resonance energy factor for the analyte, taken from 23260 32 35 references. 23260 32 36 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 32 37 (COREL,23260032) Average Q0 . 23260 32 38 ENDBIB 36 0 23260 32 39 COMMON 2 3 23260 32 40 EN-MIN-NM EN-MEAN-DN 23260 32 41 EV EV 23260 32 42 0.5 0.0253 23260 32 43 ENDCOMMON 3 0 23260 32 44 DATA 4 1 23260 32 45 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 32 46 NO-DIM PER-CENT NO-DIM PER-CENT 23260 32 47 55.8 3. 55.7 3. 23260 32 48 ENDDATA 3 0 23260 32 49 ENDSUBENT 48 0 23260 3299999 SUBENT 23260033 20141210 224123260 33 1 BIB 9 65 23260 33 2 REACTION 1((50-SN-124(N,G)50-SN-125,,RI)// 23260 33 3 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 33 4 2((50-SN-124(N,G)50-SN-125,,RI)// 23260 33 5 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 33 6 Q0 value (ratio of resonance integral to thermal 23260 33 7 neutron activation cross-section) 23260 33 8 SAMPLE Provider - IRMM 23260 33 9 Average sample thickness h,mm - 0.1 23260 33 10 Matrix - Foil, In alloy 23260 33 11 - Elemental content, % weight - 84.6 23260 33 12 - Elemental content, % weight - 94.85 23260 33 13 DECAY-DATA (50-SN-125-G,9.64D,DG,822.4,0.043,DG,915.6,0.041, 23260 33 14 DG,1067.1,0.0100,DG,1089.2,0.046) 23260 33 15 (50-SN-125-M,9.52MIN,DG,331.9,0.973) 23260 33 16 (51-SB-125,2.7586YR,DG,176.3,0.0684,DG,427.9,0.2960, 23260 33 17 DG,463.4,0.1049,DG,600.5,0.1764,DG,606.6,0.498, 23260 33 18 DG,635.9,0.1122) 23260 33 19 METHOD Measurement at channels: 23260 33 20 Y4 via Sn-125-g 23260 33 21 X26 via Sn-125-g 23260 33 22 Y4 via Sb-125 23260 33 23 X26 via Sb-125 23260 33 24 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 33 25 approaches: 23260 33 26 1- the classical method: from the mean (AVG) and 23260 33 27 observed SD of the results from all channels employed, 23260 33 28 when inputting the recommended Er value from 23260 33 29 references - 74.2 eV (+-7%). 23260 33 30 2- the a-vector method applied on up to 3 irradiation 23260 33 31 channels: leading to simultaneous Q0 (or s0) and Er 23260 33 32 determination. 23260 33 33 MISC-COL (MISC) Effective resonance energy Er defined by 23260 33 34 a-vector method. 23260 33 35 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 33 36 Uncertainty in the Q0 determination for for the simple 23260 33 37 case of one determination in one irradiation channel 23260 33 38 with one standard, given no type-B uncertainties 23260 33 39 contributions from the FCd = 1 and neutron 23260 33 40 self-shielding effects is on average 23260 33 41 2.5 % for foils, 2.6 % for compounds; 23260 33 42 include contributions from : 23260 33 43 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 33 44 for liquids/compounds in the parameter OMEGACd . 23260 33 45 - A combined type-B uncertainty from the comparator Qa 23260 33 46 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 33 47 - A combined type-B uncertainty of 1.2 % during 23260 33 48 Qa -> Q0 conversion, due to the uncertainty on a and 23260 33 49 an average 7 % uncertainty on the recommended effective23260 33 50 resonance energy factor for the analyte, taken from 23260 33 51 references. 23260 33 52 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 33 53 E-gamma,keV k0, no-dim. 23260 33 54 822.5 2.08E-7 (+-1.4%) 23260 33 55 915.6 1.88E-7 (+-1.4%) 23260 33 56 1067.1 4.64E-7 (+-1.2%) 23260 33 57 1089.2 2.50E-7 (+-1.3%) 23260 33 58 176.3 3.19E-7 (+-1.2%) 23260 33 59 427.9 1.40E-6 (+-1.8%) 23260 33 60 463.4 4.95E-7 (+-1.5%) 23260 33 61 600.5 8.28E-7 (+-1.3%) 23260 33 62 606.6 2.32E-7 (+-1.2%) 23260 33 63 635.9 5.31E-7 (+-1.7%) 23260 33 64 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 33 65 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 33 66 1(DEP,23260035) Q0 measured at different channels. 23260 33 67 ENDBIB 65 0 23260 33 68 COMMON 2 3 23260 33 69 EN-MIN-NM EN-MEAN-DN 23260 33 70 EV EV 23260 33 71 0.5 0.0253 23260 33 72 ENDCOMMON 3 0 23260 33 73 DATA 6 1 23260 33 74 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 33 75 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 33 76 34.7 2. 35.0 3. 14.6 4. 23260 33 77 ENDDATA 3 0 23260 33 78 ENDSUBENT 77 0 23260 3399999 SUBENT 23260034 20141210 224123260 34 1 BIB 7 47 23260 34 2 REACTION 1((50-SN-124(N,G)50-SN-125,,RI)// 23260 34 3 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 34 4 2((50-SN-124(N,G)50-SN-125,,RI)// 23260 34 5 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 34 6 3((50-SN-124(N,G)50-SN-125,,RI)// 23260 34 7 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 34 8 4((50-SN-124(N,G)50-SN-125,,RI)// 23260 34 9 (50-SN-124(N,G)50-SN-125,,SIG)) 23260 34 10 Q0 value (ratio of resonance integral to thermal 23260 34 11 neutron activation cross-section) 23260 34 12 SAMPLE Provider - IRMM 23260 34 13 Average sample thickness h,mm - 0.1 23260 34 14 Matrix - Foil, In alloy 23260 34 15 - Elemental content, % weight - 84.6 23260 34 16 - Elemental content, % weight - 94.85 23260 34 17 DECAY-DATA (50-SN-125-G,9.64D,DG,822.4,0.043,DG,915.6,0.041, 23260 34 18 DG,1067.1,0.0100,DG,1089.2,0.046) 23260 34 19 (50-SN-125-M,9.52MIN,DG,331.9,0.973) 23260 34 20 (51-SB-125,2.7586YR,DG,176.3,0.0684,DG,427.9,0.2960, 23260 34 21 DG,463.4,0.1049,DG,600.5,0.1764,DG,606.6,0.498, 23260 34 22 DG,635.9,0.1122) 23260 34 23 METHOD Measurement at channels: 23260 34 24 1 Y4 via Sn-125-g 23260 34 25 2 X26 via Sn-125-g 23260 34 26 3 Y4 via Sb-125 23260 34 27 4 X26 via Sb-125 23260 34 28 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 34 29 recommended Er value from references - 74.2 eV (+-7%). 23260 34 30 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 34 31 Uncertainty in the Q0 determination for for the simple 23260 34 32 case of one determination in one irradiation channel 23260 34 33 with one standard, given no type-B uncertainties 23260 34 34 contributions from the FCd = 1 and neutron 23260 34 35 self-shielding effects is on average 23260 34 36 2.5 % for foils, 2.6 % for compounds; 23260 34 37 include contributions from : 23260 34 38 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 34 39 for liquids/compounds in the parameter OMEGACd . 23260 34 40 - A combined type-B uncertainty from the comparator Qa 23260 34 41 factor for channels X26 up to 2.1 %, Y4 - 1.9 % . 23260 34 42 - A combined type-B uncertainty of 1.2 % during 23260 34 43 Qa -> Q0 conversion, due to the uncertainty on a and 23260 34 44 an average 7 % uncertainty on the recommended effective23260 34 45 resonance energy factor for the analyte, taken from 23260 34 46 references. 23260 34 47 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 34 48 (COREL,23260034) Average Q0. 23260 34 49 ENDBIB 47 0 23260 34 50 COMMON 2 3 23260 34 51 EN-MIN-NM EN-MEAN-DN 23260 34 52 EV EV 23260 34 53 0.5 0.0253 23260 34 54 ENDCOMMON 3 0 23260 34 55 DATA 8 1 23260 34 56 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 34 57 DATA 4DATA-ERR 4 23260 34 58 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 34 59 NO-DIM PER-CENT 23260 34 60 16.7 4. 16.3 3. 16.3 2. 23260 34 61 17.1 1. 23260 34 62 ENDDATA 6 0 23260 34 63 ENDSUBENT 62 0 23260 3499999 SUBENT 23260035 20141210 224123260 35 1 BIB 10 56 23260 35 2 REACTION 1((51-SB-121(N,G)51-SB-122,,RI)// 23260 35 3 (51-SB-121(N,G)51-SB-122,,SIG)) 23260 35 4 2((51-SB-121(N,G)51-SB-122,,RI)// 23260 35 5 (51-SB-121(N,G)51-SB-122,,SIG)) 23260 35 6 Q0 value (ratio of resonance integral to thermal 23260 35 7 neutron activation cross-section) 23260 35 8 SAMPLE Provider - IRMM 23260 35 9 Matrix - Foil, Al alloy 23260 35 10 Elemental content, % weight - 1. 23260 35 11 Average sample thickness h,mm - 0.1 23260 35 12 DECAY-DATA (51-SB-122-G,2.724D,DG,564.2,0.7067,DG,692.7,0.0385) 23260 35 13 REL-REF (R,,F.De Corte,T,DE CORTE,1987) 23260 35 14 The k0-standardization method: a move to the 23260 35 15 optimization of neutron activation analysis. 23260 35 16 Ph.D. Thesis. Gent Universiteit, Belgium. 23260 35 17 METHOD Measurement at channels: 23260 35 18 S84 23260 35 19 Y4 23260 35 20 X26 23260 35 21 ANALYSIS FCd=0.99 value adopted from REL-REF of F.De Corte. 23260 35 22 The Q0(or s0) factors were determined by 2 different 23260 35 23 approaches: 23260 35 24 1- the classical method: from the mean (AVG) and 23260 35 25 observed SD of the results from all channels employed, 23260 35 26 when inputting the recommended Er value from 23260 35 27 references - 13.1 eV (+-7%). 23260 35 28 2- the a-vector method applied on up to 3 irradiation 23260 35 29 channels: leading to simultaneous Q0 (or s0) and Er 23260 35 30 determination. 23260 35 31 MISC-COL (MISC) Effective resonance energy Er defined by 23260 35 32 a-vector method. 23260 35 33 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 35 34 Uncertainty in the Q0 determination for for the simple 23260 35 35 case of one determination in one irradiation channel 23260 35 36 with one standard, given no type-B uncertainties 23260 35 37 contributions from the FCd = 1 and neutron 23260 35 38 self-shielding effects is on average 23260 35 39 2.5 % for foils, 2.6 % for compounds; 23260 35 40 include contributions from : 23260 35 41 - The combined uncertainty of 1.2 % for foils and 1.2 %23260 35 42 for liquids/compounds in the parameter OMEGACd . 23260 35 43 - A combined type-B uncertainty from the comparator Qa 23260 35 44 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 35 45 S84 - 1.8 % . 23260 35 46 - A combined type-B uncertainty of 1.2 % during 23260 35 47 Qa -> Q0 conversion, due to the uncertainty on a and 23260 35 48 an average 7 % uncertainty on the recommended effective23260 35 49 resonance energy factor for the analyte, taken from 23260 35 50 references. 23260 35 51 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 35 52 E-gamma,keV k0, no-dim. 23260 35 53 564.2 4.00E-2 (+-2.0%) 23260 35 54 692.7 2.18E-3 (+-2.0%) 23260 35 55 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 35 56 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 35 57 1(DEP,23260037) Q0 measured at different channels. 23260 35 58 ENDBIB 56 0 23260 35 59 COMMON 2 3 23260 35 60 EN-MIN-NM EN-MEAN-DN 23260 35 61 EV EV 23260 35 62 0.5 0.0253 23260 35 63 ENDCOMMON 3 0 23260 35 64 DATA 6 1 23260 35 65 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 35 66 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 35 67 34.7 2. 35.0 3. 14.6 4. 23260 35 68 ENDDATA 3 0 23260 35 69 ENDSUBENT 68 0 23260 3599999 SUBENT 23260036 20141210 224123260 36 1 BIB 7 39 23260 36 2 REACTION 1((51-SB-121(N,G)51-SB-122,,RI)// 23260 36 3 (51-SB-121(N,G)51-SB-122,,SIG)) 23260 36 4 2((51-SB-121(N,G)51-SB-122,,RI)// 23260 36 5 (51-SB-121(N,G)51-SB-122,,SIG)) 23260 36 6 3((51-SB-121(N,G)51-SB-122,,RI)// 23260 36 7 (51-SB-121(N,G)51-SB-122,,SIG)) 23260 36 8 Q0 value (ratio of resonance integral to thermal 23260 36 9 neutron activation cross-section) 23260 36 10 SAMPLE Provider - IRMM 23260 36 11 Matrix - Foil, Al alloy 23260 36 12 Elemental content, % weight - 1. 23260 36 13 Average sample thickness h,mm - 0.1 23260 36 14 DECAY-DATA (51-SB-122-G,2.724D,DG,564.2,0.7067,DG,692.7,0.0385) 23260 36 15 METHOD Measurement at channels: 23260 36 16 1 S84 23260 36 17 2 Y4 23260 36 18 3 X26 23260 36 19 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 36 20 recommended Er value from references - 13.1 eV (+-7%). 23260 36 21 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 36 22 Uncertainty in the Q0 determination for for the simple 23260 36 23 case of one determination in one irradiation channel 23260 36 24 with one standard, given no type-B uncertainties 23260 36 25 contributions from the FCd = 1 and neutron 23260 36 26 self-shielding effects is on average 23260 36 27 2.5 % for foils, 2.6 % for compounds; 23260 36 28 include contributions from : 23260 36 29 - The combined uncertainty of 1.2 % for foils and 1.2 %23260 36 30 for liquids/compounds in the parameter OMEGACd . 23260 36 31 - A combined type-B uncertainty from the comparator Qa 23260 36 32 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 36 33 S84 - 1.8 % . 23260 36 34 - A combined type-B uncertainty of 1.2 % during 23260 36 35 Qa -> Q0 conversion, due to the uncertainty on a and 23260 36 36 an average 7 % uncertainty on the recommended effective23260 36 37 resonance energy factor for the analyte, taken from 23260 36 38 references. 23260 36 39 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 36 40 (COREL,23260037) Average Q0. 23260 36 41 ENDBIB 39 0 23260 36 42 COMMON 2 3 23260 36 43 EN-MIN-NM EN-MEAN-DN 23260 36 44 EV EV 23260 36 45 0.5 0.0253 23260 36 46 ENDCOMMON 3 0 23260 36 47 DATA 6 1 23260 36 48 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 36 49 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 36 50 34.8 2. 34.9 1. 34.3 1. 23260 36 51 ENDDATA 3 0 23260 36 52 ENDSUBENT 51 0 23260 3699999 SUBENT 23260037 20151013 224523260 37 1 BIB 10 67 23260 37 2 REACTION 1((51-SB-123(N,G)51-SB-124-G,M+,RI)// 23260 37 3 (51-SB-123(N,G)51-SB-124-G,M+,SIG)) 23260 37 4 2((51-SB-123(N,G)51-SB-124-G,M+,RI)// 23260 37 5 (51-SB-123(N,G)51-SB-124-G,M+,SIG)) 23260 37 6 Q0 value (ratio of resonance integral to thermal 23260 37 7 neutron activation cross-section) 23260 37 8 SAMPLE Provider - IRMM 23260 37 9 Matrix - Foil, Al alloy 23260 37 10 Elemental content, % weight - 1. 23260 37 11 Average sample thickness h,mm - 0.1 23260 37 12 DECAY-DATA (51-SB-124-G,60.2D,DG,602.7,0.978,DG,645.9,0.0742, 23260 37 13 DG,709.3,0.01353,DG,713.8,0.02276,DG,722.8,0.1076, 23260 37 14 DG,968.2,0.01882,DG,1045.1,0.01833,DG,1325.5,0.0158, 23260 37 15 DG,1368.2,0.02624,DG,1436.6,0.1217,DG,1691.0,0.4757, 23260 37 16 DG,2090.9,0.0549) 23260 37 17 METHOD Measurement at channels: 23260 37 18 S84 23260 37 19 Y4 23260 37 20 X26 23260 37 21 ANALYSIS The Q0(or s0) factors were determined by 2 different 23260 37 22 approaches: 23260 37 23 1- the classical method: from the mean (AVG) and 23260 37 24 observed SD of the results from all channels employed, 23260 37 25 when inputting the recommended Er value from 23260 37 26 references - 28.2 eV (+-7%). 23260 37 27 2- the a-vector method applied on up to 3 irradiation 23260 37 28 channels: leading to simultaneous Q0 (or s0) and Er 23260 37 29 determination. 23260 37 30 MISC-COL (MISC) Effective resonance energy Er defined by 23260 37 31 a-vector method. 23260 37 32 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 37 33 Uncertainty in the Q0 determination for the simple 23260 37 34 case of one determination in one irradiation channel 23260 37 35 with one standard, given no type-B uncertainties 23260 37 36 contributions from the FCd = 1 and neutron 23260 37 37 self-shielding effects is on average 23260 37 38 2.5 % for foils, 2.6 % for compounds; 23260 37 39 include contributions from : 23260 37 40 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 37 41 for liquids/compounds in the parameter OMEGACd . 23260 37 42 - A combined type-B uncertainty from the comparator Qa 23260 37 43 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 37 44 S84 - 1.8 % . 23260 37 45 - A combined type-B uncertainty of 1.2 % during 23260 37 46 Qa -> Q0 conversion, due to the uncertainty on a and 23260 37 47 an average 7 % uncertainty on the recommended effective23260 37 48 resonance energy factor for the analyte, taken from 23260 37 49 references. 23260 37 50 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 37 51 E-gamma,keV k0, no-dim. 23260 37 52 602.7 2.80E-2 (+-1.8%) 23260 37 53 645.9 2.11E-3 (+-1.8%) 23260 37 54 709.3 3.87E-4 (+-1.7%) 23260 37 55 713.8 6.47E-4 (+-2.0%) 23260 37 56 722.8 3.08E-3 (+-1.7%) 23260 37 57 968.2 5.43E-4 (+-1.8%) 23260 37 58 1045.1 5.22E-4 (+-2.0%) 23260 37 59 1325.5 4.46E-4 (+-1.8%) 23260 37 60 1368.2 7.50E-4 (+-1.8%) 23260 37 61 1436.6 3.48E-4 (+-3.2%) 23260 37 62 1691.0 1.38E-2 (+-1.8%) 23260 37 63 2090.9 1.58E-3 (+-1.8%) 23260 37 64 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 37 65 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 37 66 1(DEP,23260038) Q0 measured at different channels. 23260 37 67 HISTORY (20151013A) SD: SF4=Sb-124->Sb-124g, SF5=M+ (IT=75%) in23260 37 68 REACTION code following N.Otsuka's remark. 23260 37 69 ENDBIB 67 0 23260 37 70 COMMON 2 3 23260 37 71 EN-MIN-NM EN-MEAN-DN 23260 37 72 EV EV 23260 37 73 0.5 0.0253 23260 37 74 ENDCOMMON 3 0 23260 37 75 DATA 6 1 23260 37 76 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 37 77 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 37 78 30.5 2. 31.0 3. 32.4 5. 23260 37 79 ENDDATA 3 0 23260 37 80 ENDSUBENT 79 0 23260 3799999 SUBENT 23260038 20151013 224523260 38 1 BIB 8 45 23260 38 2 REACTION 1((51-SB-123(N,G)51-SB-124-G,M+,RI)// 23260 38 3 (51-SB-123(N,G)51-SB-124-G,M+,SIG)) 23260 38 4 2((51-SB-123(N,G)51-SB-124-G,M+,RI)// 23260 38 5 (51-SB-123(N,G)51-SB-124-G,M+,SIG)) 23260 38 6 3((51-SB-123(N,G)51-SB-124-G,M+,RI)// 23260 38 7 (51-SB-123(N,G)51-SB-124-G,M+,SIG)) 23260 38 8 Q0 value (ratio of resonance integral to thermal 23260 38 9 neutron activation cross-section) 23260 38 10 SAMPLE Provider - IRMM 23260 38 11 Matrix - Foil, Al alloy 23260 38 12 Elemental content, % weight - 1. 23260 38 13 Average sample thickness h,mm - 0.1 23260 38 14 DECAY-DATA (51-SB-124-G,60.2D,DG,602.7,0.978,DG,645.9,0.0742, 23260 38 15 DG,709.3,0.01353,DG,713.8,0.02276,DG,722.8,0.1076, 23260 38 16 DG,968.2,0.01882,DG,1045.1,0.01833,DG,1325.5,0.0158, 23260 38 17 DG,1368.2,0.02624,DG,1436.6,0.1217,DG,1691.0,0.4757, 23260 38 18 DG,2090.9,0.0549) 23260 38 19 METHOD Measurement at channels: 23260 38 20 1 S84 23260 38 21 2 Y4 23260 38 22 3 X26 23260 38 23 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 38 24 recommended Er value from references - 28.2 eV (+-7%). 23260 38 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 38 26 Uncertainty in the Q0 determination for the simple 23260 38 27 case of one determination in one irradiation channel 23260 38 28 with one standard, given no type-B uncertainties 23260 38 29 contributions from the FCd = 1 and neutron 23260 38 30 self-shielding effects is on average 23260 38 31 2.5 % for foils, 2.6 % for compounds; 23260 38 32 include contributions from : 23260 38 33 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 38 34 for liquids/compounds in the parameter OMEGACd . 23260 38 35 - A combined type-B uncertainty from the comparator Qa 23260 38 36 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 38 37 S84 - 1.8 % . 23260 38 38 - A combined type-B uncertainty of 1.2 % during 23260 38 39 Qa -> Q0 conversion, due to the uncertainty on a and 23260 38 40 an average 7 % uncertainty on the recommended effective23260 38 41 resonance energy factor for the analyte, taken from 23260 38 42 references. 23260 38 43 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 38 44 HISTORY (20151013A) SD: SF4=Sb-124->Sb-124g, SF5=M+ (IT=75%) in23260 38 45 REACTION code following N.Otsuka's remark. STATUS 23260 38 46 'COREL' deleted. 23260 38 47 ENDBIB 45 0 23260 38 48 COMMON 2 3 23260 38 49 EN-MIN-NM EN-MEAN-DN 23260 38 50 EV EV 23260 38 51 0.5 0.0253 23260 38 52 ENDCOMMON 3 0 23260 38 53 DATA 6 1 23260 38 54 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 38 55 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 38 56 30.8 2. 30.8 1. 30.2 1. 23260 38 57 ENDDATA 3 0 23260 38 58 ENDSUBENT 57 0 23260 3899999 SUBENT 23260039 20141210 224123260 39 1 BIB 10 52 23260 39 2 REACTION 1((56-BA-134(N,G)56-BA-135-M,,RI)// 23260 39 3 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23260 39 4 2((56-BA-134(N,G)56-BA-135-M,,RI)// 23260 39 5 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23260 39 6 Q0 value (ratio of resonance integral to thermal 23260 39 7 neutron activation cross-section) 23260 39 8 SAMPLE Provider - Sigma-Aldrich 23260 39 9 Matrix - BaO 23260 39 10 Elemental content, % weight - 89.565 23260 39 11 Average sample thickness h,mm - 0.15 23260 39 12 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.160) 23260 39 13 METHOD Measurement at channels: 23260 39 14 S84 23260 39 15 Y4 23260 39 16 X26 23260 39 17 ANALYSIS The Q0(or s0) factors were determined by 23260 39 18 approaches: 23260 39 19 1- the classical method: from the mean (AVG) and 23260 39 20 observed SD of the results from all channels employed, 23260 39 21 when inputting the recommended Er value from 23260 39 22 references - 115. eV . 23260 39 23 2- the a-vector method applied on up to 3 irradiation 23260 39 24 channels: leading to simultaneous Q0 (or s0) and Er 23260 39 25 determination. 23260 39 26 MISC-COL (MISC) Effective resonance energy Er defined by 23260 39 27 a-vector method. 23260 39 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 39 29 Uncertainty in the Q0 determination for for the simple 23260 39 30 case of one determination in one irradiation channel 23260 39 31 with one standard, given no type-B uncertainties 23260 39 32 contributions from the FCd = 1 and neutron 23260 39 33 self-shielding effects is on average 23260 39 34 2.6 % for compounds; 23260 39 35 include contributions from : 23260 39 36 - The combined uncertainty of 1.2 % 23260 39 37 for liquids/compounds in the parameter OMEGACd . 23260 39 38 - A combined type-B uncertainty from the comparator Qa 23260 39 39 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 39 40 S84 - 1.8 % . 23260 39 41 - A combined type-B uncertainty of 1.2 % during 23260 39 42 Qa -> Q0 conversion, due to the uncertainty on a and 23260 39 43 an average 7 % uncertainty on the recommended effective23260 39 44 resonance energy factor for the analyte, taken from 23260 39 45 references. 23260 39 46 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 39 47 E-gamma,keV k0, no-dim. 23260 39 48 268.3 3.21E-6 (+-3.3%) 23260 39 49 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 39 50 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 39 51 1(DEP,23260041) Q0 measured at different channels. 23260 39 52 COMMENT Of compiler. DATA 1 uncertainty in Table 5 of 23260 39 53 J,JRN,302,655,2014 is 23.%. 23260 39 54 ENDBIB 52 0 23260 39 55 COMMON 2 3 23260 39 56 EN-MIN-NM EN-MEAN-DN 23260 39 57 EV EV 23260 39 58 0.5 0.0253 23260 39 59 ENDCOMMON 3 0 23260 39 60 DATA 6 1 23260 39 61 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 39 62 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 39 63 43.5 12. 52.4 3. 5503. 20. 23260 39 64 ENDDATA 3 0 23260 39 65 ENDSUBENT 64 0 23260 3999999 SUBENT 23260040 20141210 224123260 40 1 BIB 7 39 23260 40 2 REACTION 1((56-BA-134(N,G)56-BA-135-M,,RI)// 23260 40 3 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23260 40 4 2((56-BA-134(N,G)56-BA-135-M,,RI)// 23260 40 5 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23260 40 6 3((56-BA-134(N,G)56-BA-135-M,,RI)// 23260 40 7 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23260 40 8 Q0 value (ratio of resonance integral to thermal 23260 40 9 neutron activation cross-section) 23260 40 10 SAMPLE Provider - Sigma-Aldrich 23260 40 11 Matrix - BaO 23260 40 12 Elemental content, % weight - 89.565 23260 40 13 Average sample thickness h,mm - 0.15 23260 40 14 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.160) 23260 40 15 METHOD Measurement at channels: 23260 40 16 1 S84 23260 40 17 2 Y4 23260 40 18 3 X26 23260 40 19 ANALYSIS The Q0(or s0) factors were determined by inputting the 23260 40 20 recommended Er value from references - 115. eV . 23260 40 21 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 40 22 Uncertainty in the Q0 determination for for the simple 23260 40 23 case of one determination in one irradiation channel 23260 40 24 with one standard, given no type-B uncertainties 23260 40 25 contributions from the FCd = 1 and neutron 23260 40 26 self-shielding effects is on average 23260 40 27 2.6 % for compounds; 23260 40 28 include contributions from : 23260 40 29 - The combined uncertainty of 1.2 % 23260 40 30 for liquids/compounds in the parameter OMEGACd . 23260 40 31 - A combined type-B uncertainty from the comparator Qa 23260 40 32 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 40 33 S84 - 1.8 % . 23260 40 34 - A combined type-B uncertainty of 1.2 % during 23260 40 35 Qa -> Q0 conversion, due to the uncertainty on a and 23260 40 36 an average 7 % uncertainty on the recommended effective23260 40 37 resonance energy factor for the analyte, taken from 23260 40 38 references. 23260 40 39 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 40 40 (COREL,23260040) Average Q0 . 23260 40 41 ENDBIB 39 0 23260 40 42 COMMON 2 3 23260 40 43 EN-MIN-NM EN-MEAN-DN 23260 40 44 EV EV 23260 40 45 0.5 0.0253 23260 40 46 ENDCOMMON 3 0 23260 40 47 DATA 6 1 23260 40 48 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 40 49 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 40 50 54.7 2. 39.9 1. 36.0 1. 23260 40 51 ENDDATA 3 0 23260 40 52 ENDSUBENT 51 0 23260 4099999 SUBENT 23260041 20141210 224123260 41 1 BIB 9 38 23260 41 2 REACTION ((64-GD-152(N,G)64-GD-153,,RI)// 23260 41 3 (64-GD-152(N,G)64-GD-153,,SIG)) 23260 41 4 Q0 value (ratio of resonance integral to thermal 23260 41 5 neutron activation cross-section) 23260 41 6 SAMPLE Provider - IRMM 23260 41 7 Matrix - Disk, Al alloy 23260 41 8 Elemental content, % weight - 0.03 23260 41 9 Average sample thickness h,mm - 1.6 23260 41 10 DECAY-DATA (64-GD-153,240.4D,DG,97.4,0.290,DG,103.2,0.211) 23260 41 11 METHOD Measurement at Y4 channel. 23260 41 12 ANALYSIS The Q0 factors were determined by inputting the 23260 41 13 recommended Er value from references - 16.7 eV (+-9.%).23260 41 14 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 41 15 Uncertainty in the Q0 determination for for the simple 23260 41 16 case of one determination in one irradiation channel 23260 41 17 with one standard, given no type-B uncertainties 23260 41 18 contributions from the FCd = 1 and neutron 23260 41 19 self-shielding effects is on average 23260 41 20 2.6 % for compounds; 23260 41 21 include contributions from : 23260 41 22 - The combined uncertainty of 1.2 % 23260 41 23 for liquids/compounds in the parameter OMEGACd . 23260 41 24 - A combined type-B uncertainty from the comparator Qa 23260 41 25 factor for channel Y4 - 1.9 % . 23260 41 26 - A combined type-B uncertainty of 1.2 % during 23260 41 27 Qa -> Q0 conversion, due to the uncertainty on a and 23260 41 28 an average 7 % uncertainty on the recommended effective23260 41 29 resonance energy factor for the analyte, taken from 23260 41 30 references. 23260 41 31 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 41 32 E-gamma,keV k0, no-dim. 23260 41 33 97.4 5.94E-3 (+-1.8%) 23260 41 34 103.2 4.34E-3 (+-1.9%) 23260 41 35 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 41 36 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 41 37 COMMENT Of compiler. In Table 2 of J,JRN,302,655,2014 23260 41 38 in Matrix column - alloy is marked by '*', but not 23260 41 39 by 'a' as in Table 1. 23260 41 40 ENDBIB 38 0 23260 41 41 COMMON 2 3 23260 41 42 EN-MIN-NM EN-MEAN-DN 23260 41 43 EV EV 23260 41 44 0.5 0.0253 23260 41 45 ENDCOMMON 3 0 23260 41 46 DATA 2 1 23260 41 47 DATA DATA-ERR 23260 41 48 NO-DIM PER-CENT 23260 41 49 0.56 5. 23260 41 50 ENDDATA 3 0 23260 41 51 ENDSUBENT 50 0 23260 4199999 SUBENT 23260042 20141210 224123260 42 1 BIB 9 37 23260 42 2 REACTION ((64-GD-158(N,G)64-GD-159,,RI)// 23260 42 3 (64-GD-158(N,G)64-GD-159,,SIG)) 23260 42 4 Q0 value (ratio of resonance integral to thermal 23260 42 5 neutron activation cross-section) 23260 42 6 SAMPLE Provider - IRMM 23260 42 7 Matrix - Disk, Al alloy 23260 42 8 Elemental content, % weight - 0.03 23260 42 9 Average sample thickness h,mm - 1.6 23260 42 10 DECAY-DATA (64-GD-159,18.56HR,DG,363.5,0.1178) 23260 42 11 METHOD Measurement at Y4 channel. 23260 42 12 ANALYSIS The Q0 factors were determined by inputting the 23260 42 13 recommended Er value from references - 48.2 eV (+-8.%).23260 42 14 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 42 15 Uncertainty in the Q0 determination for for the simple 23260 42 16 case of one determination in one irradiation channel 23260 42 17 with one standard, given no type-B uncertainties 23260 42 18 contributions from the FCd = 1 and neutron 23260 42 19 self-shielding effects is on average 23260 42 20 2.6 % for compounds; 23260 42 21 include contributions from : 23260 42 22 - The combined uncertainty of 1.2 % 23260 42 23 for liquids/compounds in the parameter OMEGACd . 23260 42 24 - A combined type-B uncertainty from the comparator Qa 23260 42 25 factor for channel Y4 - 1.9 % . 23260 42 26 - A combined type-B uncertainty of 1.2 % during 23260 42 27 Qa -> Q0 conversion, due to the uncertainty on a and 23260 42 28 an average 7 % uncertainty on the recommended effective23260 42 29 resonance energy factor for the analyte, taken from 23260 42 30 references. 23260 42 31 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 42 32 E-gamma,keV k0, no-dim. 23260 42 33 363.5 8.63E-4 (+-1.8%) 23260 42 34 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 42 35 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 42 36 COMMENT Of compiler. In Table 2 of J,JRN,302,655,2014 23260 42 37 in Matrix column - alloy is marked by '*', but not 23260 42 38 by 'a' as in Table 1. 23260 42 39 ENDBIB 37 0 23260 42 40 COMMON 2 3 23260 42 41 EN-MIN-NM EN-MEAN-DN 23260 42 42 EV EV 23260 42 43 0.5 0.0253 23260 42 44 ENDCOMMON 3 0 23260 42 45 DATA 2 1 23260 42 46 DATA DATA-ERR 23260 42 47 NO-DIM PER-CENT 23260 42 48 31.2 5. 23260 42 49 ENDDATA 3 0 23260 42 50 ENDSUBENT 49 0 23260 4299999 SUBENT 23260043 20141210 224123260 43 1 BIB 10 61 23260 43 2 REACTION 1((66-DY-164(N,G)66-DY-165,,RI)// 23260 43 3 (66-DY-164(N,G)66-DY-165,,SIG)) 23260 43 4 2((66-DY-164(N,G)66-DY-165,,RI)// 23260 43 5 (66-DY-164(N,G)66-DY-165,,SIG)) 23260 43 6 Q0 value (ratio of resonance integral to thermal 23260 43 7 neutron activation cross-section) 23260 43 8 SAMPLE Provider - IRMM 23260 43 9 Matrix - Foil, Al alloy 23260 43 10 Average sample thickness h,mm - 0.1 23260 43 11 - Elemental content, % weight - 27. 23260 43 12 - Elemental content, % weight - 5. 23260 43 13 - Elemental content, % weight - 0.127 23260 43 14 DECAY-DATA (66-DY-165-G,2.334HR,DG,94.7,0.0380,DG,279.8,0.0053, 23260 43 15 DG,361.7,0.0090,DG,633.4,0.0061,DG,715.3,0.0058) 23260 43 16 METHOD Measurement at channels: 23260 43 17 S84 23260 43 18 X26 23260 43 19 ANALYSIS The Q0(or s0) factors were determined by 23260 43 20 approaches: 23260 43 21 1- the classical method: from the mean (AVG) and 23260 43 22 observed SD of the results from all channels employed, 23260 43 23 when inputting the recommended Er value from 23260 43 24 references - 224. eV (+-5.%) . 23260 43 25 2- the a-vector method applied on up to 3 irradiation 23260 43 26 channels: leading to simultaneous Q0 (or s0) and Er 23260 43 27 determination. 23260 43 28 MISC-COL (MISC) Effective resonance energy Er defined by 23260 43 29 a-vector method. 23260 43 30 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 43 31 Uncertainty in the Q0 determination for for the simple 23260 43 32 case of one determination in one irradiation channel 23260 43 33 with one standard, given no type-B uncertainties 23260 43 34 contributions from the FCd = 1 and neutron 23260 43 35 self-shielding effects is on average 23260 43 36 2.5 % for foils, 2.6 % for compounds; 23260 43 37 include contributions from : 23260 43 38 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 43 39 for liquids/compounds in the parameter OMEGACd . 23260 43 40 - A combined type-B uncertainty from the comparator Qa 23260 43 41 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 43 42 - A combined type-B uncertainty of 1.2 % during 23260 43 43 Qa -> Q0 conversion, due to the uncertainty on a and 23260 43 44 an average 7 % uncertainty on the recommended effective23260 43 45 resonance energy factor for the analyte, taken from 23260 43 46 references. 23260 43 47 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 43 48 E-gamma,keV k0, no-dim. 23260 43 49 94.7 3.62E-1 (+-1.1%) 23260 43 50 279.8 5.13E-2 (+-1.2%) 23260 43 51 361.7 8.66E-2 (+-1.0%) 23260 43 52 633.4 5.79E-2 (+-1.1%) 23260 43 53 715.3 5.43E-2 (+-1.3%) 23260 43 54 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 43 55 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 43 56 1(DEP,23260047) Q0 measured at different channels. 23260 43 57 COMMENT Of compiler. 23260 43 58 - DATA 1 uncertainty in Table 5 of 23260 43 59 J,JRN,302,655,2014 is 21.% ( misprint ?). 23260 43 60 - In Table 2 of J,JRN,302,655,2014 23260 43 61 in Matrix column - alloy is marked by '*', but not 23260 43 62 by 'a' as in Table 1. 23260 43 63 ENDBIB 61 0 23260 43 64 COMMON 2 3 23260 43 65 EN-MIN-NM EN-MEAN-DN 23260 43 66 EV EV 23260 43 67 0.5 0.0253 23260 43 68 ENDCOMMON 3 0 23260 43 69 DATA 6 1 23260 43 70 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 43 71 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 43 72 0.13 22. 0.72 3. 28.9 25. 23260 43 73 ENDDATA 3 0 23260 43 74 ENDSUBENT 73 0 23260 4399999 SUBENT 23260044 20141210 224123260 44 1 BIB 8 42 23260 44 2 REACTION 1((66-DY-164(N,G)66-DY-165,,RI)// 23260 44 3 (66-DY-164(N,G)66-DY-165,,SIG)) 23260 44 4 2((66-DY-164(N,G)66-DY-165,,RI)// 23260 44 5 (66-DY-164(N,G)66-DY-165,,SIG)) 23260 44 6 Q0 value (ratio of resonance integral to thermal 23260 44 7 neutron activation cross-section) 23260 44 8 SAMPLE Provider - IRMM 23260 44 9 Matrix - Foil, Al alloy 23260 44 10 Average sample thickness h,mm - 0.1 23260 44 11 - Elemental content, % weight - 27. 23260 44 12 - Elemental content, % weight - 5. 23260 44 13 - Elemental content, % weight - 0.127 23260 44 14 DECAY-DATA (66-DY-165-G,2.334HR,DG,94.7,0.0380,DG,279.8,0.0053, 23260 44 15 DG,361.7,0.0090,DG,633.4,0.0061,DG,715.3,0.0058) 23260 44 16 METHOD Measurement at channels: 23260 44 17 1 S84 23260 44 18 2 X26 23260 44 19 ANALYSIS The Q0 factors were determined by inputting the 23260 44 20 recommended Er value from references - 224. eV (+-5.%) 23260 44 21 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 44 22 Uncertainty in the Q0 determination for for the simple 23260 44 23 case of one determination in one irradiation channel 23260 44 24 with one standard, given no type-B uncertainties 23260 44 25 contributions from the FCd = 1 and neutron 23260 44 26 self-shielding effects is on average 23260 44 27 2.5 % for foils, 2.6 % for compounds; 23260 44 28 include contributions from : 23260 44 29 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 44 30 for liquids/compounds in the parameter OMEGACd . 23260 44 31 - A combined type-B uncertainty from the comparator Qa 23260 44 32 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 44 33 - A combined type-B uncertainty of 1.2 % during 23260 44 34 Qa -> Q0 conversion, due to the uncertainty on a and 23260 44 35 an average 7 % uncertainty on the recommended effective23260 44 36 resonance energy factor for the analyte, taken from 23260 44 37 references. 23260 44 38 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 44 39 (COREL,23260046) Average Q0 . 23260 44 40 COMMENT Of compiler. 23260 44 41 - In Table 2 of J,JRN,302,655,2014 23260 44 42 in Matrix column - alloy is marked by '*', but not 23260 44 43 by 'a' as in Table 1. 23260 44 44 ENDBIB 42 0 23260 44 45 COMMON 2 3 23260 44 46 EN-MIN-NM EN-MEAN-DN 23260 44 47 EV EV 23260 44 48 0.5 0.0253 23260 44 49 ENDCOMMON 3 0 23260 44 50 DATA 4 1 23260 44 51 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 44 52 NO-DIM PER-CENT NO-DIM PER-CENT 23260 44 53 0.14 8. 0.07 7. 23260 44 54 ENDDATA 3 0 23260 44 55 ENDSUBENT 54 0 23260 4499999 SUBENT 23260045 20141210 224123260 45 1 BIB 8 34 23260 45 2 REACTION ((69-TM-169(N,G)69-TM-170,,RI)// 23260 45 3 (69-TM-169(N,G)69-TM-170,,SIG)) 23260 45 4 Q0 value (ratio of resonance integral to thermal 23260 45 5 neutron activation cross-section) 23260 45 6 SAMPLE Provider - Alfa Aesar 23260 45 7 Matrix - Liquid on paper 23260 45 8 Elemental content, % weight - 0.1 23260 45 9 Average sample thickness h,mm - 1.25 23260 45 10 DECAY-DATA (69-TM-170,128.6D,DG,84.3,0.0248) 23260 45 11 METHOD Measurement at Y4 channel. 23260 45 12 ANALYSIS The Q0 factors were determined by inputting the 23260 45 13 recommended Er value from references - 4.8 eV (+-2.%). 23260 45 14 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 45 15 Uncertainty in the Q0 determination for for the simple 23260 45 16 case of one determination in one irradiation channel 23260 45 17 with one standard, given no type-B uncertainties 23260 45 18 contributions from the FCd = 1 and neutron 23260 45 19 self-shielding effects is on average 23260 45 20 2.6 % for compounds; 23260 45 21 include contributions from : 23260 45 22 - The combined uncertainty of 1.2 % 23260 45 23 for liquids/compounds in the parameter OMEGACd . 23260 45 24 - A combined type-B uncertainty from the comparator Qa 23260 45 25 factor for channels Y4 - 1.9 % . 23260 45 26 - A combined type-B uncertainty of 1.2 % during 23260 45 27 Qa -> Q0 conversion, due to the uncertainty on a and 23260 45 28 an average 7 % uncertainty on the recommended effective23260 45 29 resonance energy factor for the analyte, taken from 23260 45 30 references. 23260 45 31 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 45 32 E-gamma,keV k0, no-dim. 23260 45 33 84.3 3.29E-2 (+-7.1%) 23260 45 34 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 45 35 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 45 36 ENDBIB 34 0 23260 45 37 COMMON 2 3 23260 45 38 EN-MIN-NM EN-MEAN-DN 23260 45 39 EV EV 23260 45 40 0.5 0.0253 23260 45 41 ENDCOMMON 3 0 23260 45 42 DATA 2 1 23260 45 43 DATA DATA-ERR 23260 45 44 NO-DIM PER-CENT 23260 45 45 13.3 3. 23260 45 46 ENDDATA 3 0 23260 45 47 ENDSUBENT 46 0 23260 4599999 SUBENT 23260046 20141210 224123260 46 1 BIB 9 56 23260 46 2 REACTION 1((70-YB-174(N,G)70-YB-175,,RI)// 23260 46 3 (70-YB-174(N,G)70-YB-175,,SIG)) 23260 46 4 2((70-YB-174(N,G)70-YB-175,,RI)// 23260 46 5 (70-YB-174(N,G)70-YB-175,,SIG)) 23260 46 6 Q0 value (ratio of resonance integral to thermal 23260 46 7 neutron activation cross-section) 23260 46 8 SAMPLE Provider - Alfa Aesar 23260 46 9 Matrix - Liquid on paper 23260 46 10 Elemental content, % weight - 0.1 23260 46 11 Average sample thickness h,mm - 1.25 23260 46 12 DECAY-DATA (70-YB-175,4.185D,DG,113.8,0.0387,DG,137.7,0.00235, 23260 46 13 DG,144.9,0.00672,DG,282.5,0.0613,DG,396.3,0.132) 23260 46 14 METHOD Measurement at channels: 23260 46 15 S84 23260 46 16 Y4 23260 46 17 X26 23260 46 18 ANALYSIS The Q0 factors were determined by 23260 46 19 approaches: 23260 46 20 1- the classical method: from the mean (AVG) and 23260 46 21 observed SD of the results from all channels employed, 23260 46 22 when inputting the recommended Er value from 23260 46 23 references - 602. eV (+-8.%) . 23260 46 24 2- the a-vector method applied on up to 3 irradiation 23260 46 25 channels: leading to simultaneous Q0 and Er 23260 46 26 determination. 23260 46 27 MISC-COL (MISC) Effective resonance energy Er defined by 23260 46 28 a-vector method. 23260 46 29 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 46 30 Uncertainty in the Q0 determination for for the simple 23260 46 31 case of one determination in one irradiation channel 23260 46 32 with one standard, given no type-B uncertainties 23260 46 33 contributions from the FCd = 1 and neutron 23260 46 34 self-shielding effects is on average 23260 46 35 2.5 % for foils, 2.6 % for compounds; 23260 46 36 include contributions from : 23260 46 37 - The combined uncertainty of 1.2 % 23260 46 38 for liquids/compounds in the parameter OMEGACd . 23260 46 39 - A combined type-B uncertainty from the comparator Qa 23260 46 40 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 46 41 S84 - 1.8 % . 23260 46 42 - A combined type-B uncertainty of 1.2 % during 23260 46 43 Qa -> Q0 conversion, due to the uncertainty on a and 23260 46 44 an average 7 % uncertainty on the recommended effective23260 46 45 resonance energy factor for the analyte, taken from 23260 46 46 references. 23260 46 47 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 46 48 E-gamma,keV k0, no-dim. 23260 46 49 113.8 9.47E-3 (+-2.0%) 23260 46 50 137.7 5.74E-4 (+-2.4%) 23260 46 51 144.9 1.63E-3 (+-2.1%) 23260 46 52 282.5 1.50E-2 (+-2.2%) 23260 46 53 396.3 3.18E-2 (+-2.1%) 23260 46 54 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 46 55 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 46 56 Table 6 of J,JRN,302,631,2014. 23260 46 57 1(DEP,23260051) Q0 measured at different channels. 23260 46 58 ENDBIB 56 0 23260 46 59 COMMON 2 3 23260 46 60 EN-MIN-NM EN-MEAN-DN 23260 46 61 EV EV 23260 46 62 0.5 0.0253 23260 46 63 ENDCOMMON 3 0 23260 46 64 DATA 6 1 23260 46 65 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 46 66 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 46 67 0.28 18. 0.48 3. 0.115 30. 23260 46 68 ENDDATA 3 0 23260 46 69 ENDSUBENT 68 0 23260 4699999 SUBENT 23260047 20141210 224123260 47 1 BIB 7 41 23260 47 2 REACTION 1((70-YB-174(N,G)70-YB-175,,RI)// 23260 47 3 (70-YB-174(N,G)70-YB-175,,SIG)) 23260 47 4 2((70-YB-174(N,G)70-YB-175,,RI)// 23260 47 5 (70-YB-174(N,G)70-YB-175,,SIG)) 23260 47 6 3((70-YB-174(N,G)70-YB-175,,RI)// 23260 47 7 (70-YB-174(N,G)70-YB-175,,SIG)) 23260 47 8 Q0 value (ratio of resonance integral to thermal 23260 47 9 neutron activation cross-section) 23260 47 10 SAMPLE Provider - Alfa Aesar 23260 47 11 Matrix - Liquid on paper 23260 47 12 Elemental content, % weight - 0.1 23260 47 13 Average sample thickness h,mm - 1.25 23260 47 14 DECAY-DATA (70-YB-175,4.185D,DG,113.8,0.0387,DG,137.7,0.00235, 23260 47 15 DG,144.9,0.00672,DG,282.5,0.0613,DG,396.3,0.132) 23260 47 16 METHOD Measurement at channels: 23260 47 17 1 S84 23260 47 18 2 Y4 23260 47 19 3 X26 23260 47 20 ANALYSIS The Q0 factors were determined by inputting the 23260 47 21 recommended Er value from references - 602. eV (+-8.%).23260 47 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 47 23 Uncertainty in the Q0 determination for for the simple 23260 47 24 case of one determination in one irradiation channel 23260 47 25 with one standard, given no type-B uncertainties 23260 47 26 contributions from the FCd = 1 and neutron 23260 47 27 self-shielding effects is on average 23260 47 28 2.5 % for foils, 2.6 % for compounds; 23260 47 29 include contributions from : 23260 47 30 - The combined uncertainty of 1.2 % 23260 47 31 for liquids/compounds in the parameter OMEGACd . 23260 47 32 - A combined type-B uncertainty from the comparator Qa 23260 47 33 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 47 34 S84 - 1.8 % . 23260 47 35 - A combined type-B uncertainty of 1.2 % during 23260 47 36 Qa -> Q0 conversion, due to the uncertainty on a and 23260 47 37 an average 7 % uncertainty on the recommended effective23260 47 38 resonance energy factor for the analyte, taken from 23260 47 39 references. 23260 47 40 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 47 41 Table 6 of J,JRN,302,631,2014. 23260 47 42 (COREL,23260051) Average Q0 . 23260 47 43 ENDBIB 41 0 23260 47 44 COMMON 2 3 23260 47 45 EN-MIN-NM EN-MEAN-DN 23260 47 46 EV EV 23260 47 47 0.5 0.0253 23260 47 48 ENDCOMMON 3 0 23260 47 49 DATA 6 1 23260 47 50 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 47 51 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 47 52 0.39 5. 0.34 3. 0.53 5. 23260 47 53 ENDDATA 3 0 23260 47 54 ENDSUBENT 53 0 23260 4799999 SUBENT 23260048 20141210 224123260 48 1 BIB 10 55 23260 48 2 REACTION 1((70-YB-176(N,G)70-YB-177,,RI)// 23260 48 3 (70-YB-176(N,G)70-YB-177,,SIG)) 23260 48 4 2((70-YB-176(N,G)70-YB-177,,RI)// 23260 48 5 (70-YB-176(N,G)70-YB-177,,SIG)) 23260 48 6 Q0 value (ratio of resonance integral to thermal 23260 48 7 neutron activation cross-section) 23260 48 8 SAMPLE Provider - Alfa Aesar 23260 48 9 Matrix - Liquid on paper 23260 48 10 Elemental content, % weight - 0.1 23260 48 11 Average sample thickness h,mm - 1.25 23260 48 12 DECAY-DATA (70-YB-177-G,1.911HR,DG,150.3,0.205,DG,941.8,0.0108, 23260 48 13 DG,1080.2,0.059,DG,1241.2,0.0350) 23260 48 14 METHOD Measurement at channels: 23260 48 15 S84 23260 48 16 X26 23260 48 17 ANALYSIS The Q0 factors were determined by 23260 48 18 approaches: 23260 48 19 1- the classical method: from the mean (AVG) and 23260 48 20 observed SD of the results from all channels employed, 23260 48 21 when inputting the recommended Er value from 23260 48 22 references - 412. eV (+-5.%) . 23260 48 23 2- the a-vector method applied on up to 3 irradiation 23260 48 24 channels: leading to simultaneous Q0 and Er 23260 48 25 determination. 23260 48 26 MISC-COL (MISC) Effective resonance energy Er defined by 23260 48 27 a-vector method. 23260 48 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 48 29 Uncertainty in the Q0 determination for for the simple 23260 48 30 case of one determination in one irradiation channel 23260 48 31 with one standard, given no type-B uncertainties 23260 48 32 contributions from the FCd = 1 and neutron 23260 48 33 self-shielding effects is on average 23260 48 34 2.5 % for foils, 2.6 % for compounds; 23260 48 35 include contributions from : 23260 48 36 - The combined uncertainty of 1.2 % 23260 48 37 for liquids/compounds in the parameter OMEGACd . 23260 48 38 - A combined type-B uncertainty from the comparator Qa 23260 48 39 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 48 40 - A combined type-B uncertainty of 1.2 % during 23260 48 41 Qa -> Q0 conversion, due to the uncertainty on a and 23260 48 42 an average 7 % uncertainty on the recommended effective23260 48 43 resonance energy factor for the analyte, taken from 23260 48 44 references. 23260 48 45 COMMENT Of compiler. DATA 1 uncertainty in Table 5 of 23260 48 46 J,JRN,302,655,2014 is 4.%. 23260 48 47 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 48 48 E-gamma,keV k0, no-dim. 23260 48 49 150.3 9.01E-4 (+-2.0%) 23260 48 50 941.8 4.89E-5 (+-2.0%) 23260 48 51 1080.2 2.64E-4 (+-2.0%) 23260 48 52 1241.2 1.59E-4 (+-2.0%) 23260 48 53 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 48 54 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 48 55 Table 6 of J,JRN,302,631,2014. 23260 48 56 1(DEP,23260053) Q0 measured at different channels. 23260 48 57 ENDBIB 55 0 23260 48 58 COMMON 2 3 23260 48 59 EN-MIN-NM EN-MEAN-DN 23260 48 60 EV EV 23260 48 61 0.5 0.0253 23260 48 62 ENDCOMMON 3 0 23260 48 63 DATA 6 1 23260 48 64 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 48 65 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 48 66 2.51 3. 2.43 4. 190. 25. 23260 48 67 ENDDATA 3 0 23260 48 68 ENDSUBENT 67 0 23260 4899999 SUBENT 23260049 20141210 224123260 49 1 BIB 7 38 23260 49 2 REACTION 1((70-YB-176(N,G)70-YB-177,,RI)// 23260 49 3 (70-YB-176(N,G)70-YB-177,,SIG)) 23260 49 4 2((70-YB-176(N,G)70-YB-177,,RI)// 23260 49 5 (70-YB-176(N,G)70-YB-177,,SIG)) 23260 49 6 Q0 value (ratio of resonance integral to thermal 23260 49 7 neutron activation cross-section) 23260 49 8 SAMPLE Provider - Alfa Aesar 23260 49 9 Matrix - Liquid on paper 23260 49 10 Elemental content, % weight - 0.1 23260 49 11 Average sample thickness h,mm - 1.25 23260 49 12 DECAY-DATA (70-YB-177-G,1.911HR,DG,150.3,0.205,DG,941.8,0.0108, 23260 49 13 DG,1080.2,0.059,DG,1241.2,0.0350) 23260 49 14 METHOD Measurement at channels: 23260 49 15 1 S84 23260 49 16 2 X26 23260 49 17 ANALYSIS The Q0 factors were determined by inputting the 23260 49 18 recommended Er value from references - 412. eV (+-5.%).23260 49 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 49 20 Uncertainty in the Q0 determination for for the simple 23260 49 21 case of one determination in one irradiation channel 23260 49 22 with one standard, given no type-B uncertainties 23260 49 23 contributions from the FCd = 1 and neutron 23260 49 24 self-shielding effects is on average 23260 49 25 2.5 % for foils, 2.6 % for compounds; 23260 49 26 include contributions from : 23260 49 27 - The combined uncertainty of 1.2 % 23260 49 28 for liquids/compounds in the parameter OMEGACd . 23260 49 29 - A combined type-B uncertainty from the comparator Qa 23260 49 30 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 49 31 - A combined type-B uncertainty of 1.2 % during 23260 49 32 Qa -> Q0 conversion, due to the uncertainty on a and 23260 49 33 an average 7 % uncertainty on the recommended effective23260 49 34 resonance energy factor for the analyte, taken from 23260 49 35 references. 23260 49 36 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 49 37 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 49 38 Table 6 of J,JRN,302,631,2014. 23260 49 39 2(COREL,23260052) Average Q0 . 23260 49 40 ENDBIB 38 0 23260 49 41 COMMON 2 3 23260 49 42 EN-MIN-NM EN-MEAN-DN 23260 49 43 EV EV 23260 49 44 0.5 0.0253 23260 49 45 ENDCOMMON 3 0 23260 49 46 DATA 4 1 23260 49 47 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 49 48 NO-DIM PER-CENT NO-DIM PER-CENT 23260 49 49 2.42 3. 2.60 3. 23260 49 50 ENDDATA 3 0 23260 49 51 ENDSUBENT 50 0 23260 4999999 SUBENT 23260050 20141210 224123260 50 1 BIB 9 51 23260 50 2 REACTION 1((72-HF-174(N,G)72-HF-175,,RI)// 23260 50 3 (72-HF-174(N,G)72-HF-175,,SIG)) 23260 50 4 2((72-HF-174(N,G)72-HF-175,,RI)// 23260 50 5 (72-HF-174(N,G)72-HF-175,,SIG)) 23260 50 6 Q0 value (ratio of resonance integral to thermal 23260 50 7 neutron activation cross-section) 23260 50 8 SAMPLE Provider - IRMM 23260 50 9 Matrix - Wire,Al alloy 23260 50 10 Average sample thickness h,mm - 1. 23260 50 11 -Elemental content, % weight - 5. 23260 50 12 -Elemental content, % weight - 0.1 23260 50 13 DECAY-DATA (72-HF-175,70.D,DG,343.4,0.870) 23260 50 14 METHOD Measurement at channels: 23260 50 15 S84 23260 50 16 Y4 23260 50 17 X26 23260 50 18 ANALYSIS The Q0 factors were determined by approaches: 23260 50 19 1- the classical method: from the mean (AVG) and 23260 50 20 observed SD of the results from all channels employed, 23260 50 21 when inputting the recommended Er value from 23260 50 22 references - 30. eV (+-7.%) . 23260 50 23 2- the a-vector method applied on up to 3 irradiation 23260 50 24 channels: leading to simultaneous Q0 and Er 23260 50 25 determination. 23260 50 26 MISC-COL (MISC) Effective resonance energy Er defined by 23260 50 27 a-vector method. 23260 50 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 50 29 Uncertainty in the Q0 determination for for the simple 23260 50 30 case of one determination in one irradiation channel 23260 50 31 with one standard, given no type-B uncertainties 23260 50 32 contributions from the FCd = 1 and neutron 23260 50 33 self-shielding effects is on average 23260 50 34 2.5 % for foils, 2.6 % for compounds; 23260 50 35 include contributions from : 23260 50 36 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 50 37 for liquids/compounds in the parameter OMEGACd . 23260 50 38 - A combined type-B uncertainty from the comparator Qa 23260 50 39 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 50 40 S84 - 1.8 % . 23260 50 41 - A combined type-B uncertainty of 1.2 % during 23260 50 42 Qa -> Q0 conversion, due to the uncertainty on a and 23260 50 43 an average 7 % uncertainty on the recommended effective23260 50 44 resonance energy factor for the analyte, taken from 23260 50 45 references. 23260 50 46 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 50 47 E-gamma,keV k0, no-dim. 23260 50 48 343.4 8.95E-3 (+-1.4%) 23260 50 49 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 50 50 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 50 51 Table 6 of J,JRN,302,631,2014. 23260 50 52 1(DEP,23260055) Q0 measured at different channels. 23260 50 53 ENDBIB 51 0 23260 50 54 COMMON 2 3 23260 50 55 EN-MIN-NM EN-MEAN-DN 23260 50 56 EV EV 23260 50 57 0.5 0.0253 23260 50 58 ENDCOMMON 3 0 23260 50 59 DATA 6 1 23260 50 60 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 50 61 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 50 62 0.61 3. 0.64 2. 200. 22. 23260 50 63 ENDDATA 3 0 23260 50 64 ENDSUBENT 63 0 23260 5099999 SUBENT 23260051 20141210 224123260 51 1 BIB 7 41 23260 51 2 REACTION 1((72-HF-174(N,G)72-HF-175,,RI)// 23260 51 3 (72-HF-174(N,G)72-HF-175,,SIG)) 23260 51 4 2((72-HF-174(N,G)72-HF-175,,RI)// 23260 51 5 (72-HF-174(N,G)72-HF-175,,SIG)) 23260 51 6 3((72-HF-174(N,G)72-HF-175,,RI)// 23260 51 7 (72-HF-174(N,G)72-HF-175,,SIG)) 23260 51 8 Q0 value (ratio of resonance integral to thermal 23260 51 9 neutron activation cross-section) 23260 51 10 SAMPLE Provider - IRMM 23260 51 11 Matrix - Wire,Al alloy 23260 51 12 Average sample thickness h,mm - 1. 23260 51 13 -Elemental content, % weight - 5. 23260 51 14 -Elemental content, % weight - 0.1 23260 51 15 DECAY-DATA (72-HF-175,70.D,DG,343.4,0.870) 23260 51 16 METHOD Measurement at channels: 23260 51 17 1 S84 23260 51 18 2 Y4 23260 51 19 3 X26 23260 51 20 ANALYSIS The Q0 factors were determined by inputting the 23260 51 21 recommended Er value from references - 30. eV (+-7.%). 23260 51 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 51 23 Uncertainty in the Q0 determination for for the simple 23260 51 24 case of one determination in one irradiation channel 23260 51 25 with one standard, given no type-B uncertainties 23260 51 26 contributions from the FCd = 1 and neutron 23260 51 27 self-shielding effects is on average 23260 51 28 2.5 % for foils, 2.6 % for compounds; 23260 51 29 include contributions from : 23260 51 30 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 51 31 for liquids/compounds in the parameter OMEGACd . 23260 51 32 - A combined type-B uncertainty from the comparator Qa 23260 51 33 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 51 34 S84 - 1.8 % . 23260 51 35 - A combined type-B uncertainty of 1.2 % during 23260 51 36 Qa -> Q0 conversion, due to the uncertainty on a and 23260 51 37 an average 7 % uncertainty on the recommended effective23260 51 38 resonance energy factor for the analyte, taken from 23260 51 39 references. 23260 51 40 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 51 41 Table 6 of J,JRN,302,631,2014. 23260 51 42 (COREL,23260054) Average Q0 . 23260 51 43 ENDBIB 41 0 23260 51 44 COMMON 2 3 23260 51 45 EN-MIN-NM EN-MEAN-DN 23260 51 46 EV EV 23260 51 47 0.5 0.0253 23260 51 48 ENDCOMMON 3 0 23260 51 49 DATA 6 1 23260 51 50 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 51 51 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 51 52 0.64 2. 0.60 2. 0.60 4. 23260 51 53 ENDDATA 3 0 23260 51 54 ENDSUBENT 53 0 23260 5199999 SUBENT 23260052 20141210 224123260 52 1 BIB 9 57 23260 52 2 REACTION 1((72-HF-179(N,G)72-HF-180-M,,RI)// 23260 52 3 (72-HF-179(N,G)72-HF-180-M,,SIG)) 23260 52 4 2((72-HF-179(N,G)72-HF-180-M,,RI)// 23260 52 5 (72-HF-179(N,G)72-HF-180-M,,SIG)) 23260 52 6 Q0 value (ratio of resonance integral to thermal 23260 52 7 neutron activation cross-section) 23260 52 8 SAMPLE Provider - IRMM 23260 52 9 Matrix - Wire,Al alloy 23260 52 10 Average sample thickness h,mm - 1. 23260 52 11 -Elemental content, % weight - 5. 23260 52 12 -Elemental content, % weight - 0.1 23260 52 13 DECAY-DATA (72-HF-180-M,5.5HR,DG,93.3,0.171,DG,215.4,0.813, 23260 52 14 DG,332.3,0.941,DG,443.2,0.819,DG,500.7,0.143) 23260 52 15 METHOD Measurement at channels: 23260 52 16 S84 23260 52 17 Y4 23260 52 18 X26 23260 52 19 ANALYSIS The Q0 factors were determined by 23260 52 20 approaches: 23260 52 21 1- the classical method: from the mean (AVG) and 23260 52 22 observed SD of the results from all channels employed, 23260 52 23 when inputting the recommended Er value from 23260 52 24 references - 16.2 eV (+-12.%) . 23260 52 25 2- the a-vector method applied on up to 3 irradiation 23260 52 26 channels: leading to simultaneous Q0 and Er 23260 52 27 determination. 23260 52 28 MISC-COL (MISC) Effective resonance energy Er defined by 23260 52 29 a-vector method. 23260 52 30 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 52 31 Uncertainty in the Q0 determination for for the simple 23260 52 32 case of one determination in one irradiation channel 23260 52 33 with one standard, given no type-B uncertainties 23260 52 34 contributions from the FCd = 1 and neutron 23260 52 35 self-shielding effects is on average 23260 52 36 2.5 % for foils, 2.6 % for compounds; 23260 52 37 include contributions from : 23260 52 38 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 52 39 for liquids/compounds in the parameter OMEGACd . 23260 52 40 - A combined type-B uncertainty from the comparator Qa 23260 52 41 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 52 42 S84 - 1.8 % . 23260 52 43 - A combined type-B uncertainty of 1.2 % during 23260 52 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 52 45 an average 7 % uncertainty on the recommended effective23260 52 46 resonance energy factor for the analyte, taken from 23260 52 47 references. 23260 52 48 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 52 49 E-gamma,keV k0, no-dim. 23260 52 50 93.3 1.19E-4 (+-1.6%) 23260 52 51 215.4 5.61E-4 (+-1.3%) 23260 52 52 332.3 6.42E-4 (+-1.3%) 23260 52 53 443.2 5.62E-4 (+-1.3%) 23260 52 54 500.7 9.67E-5 (+-1.3%) 23260 52 55 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 52 56 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 52 57 Table 6 of J,JRN,302,631,2014. 23260 52 58 1(DEP,23260057) Q0 measured at different channels. 23260 52 59 ENDBIB 57 0 23260 52 60 COMMON 2 3 23260 52 61 EN-MIN-NM EN-MEAN-DN 23260 52 62 EV EV 23260 52 63 0.5 0.0253 23260 52 64 ENDCOMMON 3 0 23260 52 65 DATA 6 1 23260 52 66 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 52 67 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 52 68 14.1 2. 14.0 2. 12.1 15. 23260 52 69 ENDDATA 3 0 23260 52 70 ENDSUBENT 69 0 23260 5299999 SUBENT 23260053 20141210 224123260 53 1 BIB 7 42 23260 53 2 REACTION 1((72-HF-179(N,G)72-HF-180-M,,RI)// 23260 53 3 (72-HF-179(N,G)72-HF-180-M,,SIG)) 23260 53 4 2((72-HF-179(N,G)72-HF-180-M,,RI)// 23260 53 5 (72-HF-179(N,G)72-HF-180-M,,SIG)) 23260 53 6 3((72-HF-179(N,G)72-HF-180-M,,RI)// 23260 53 7 (72-HF-179(N,G)72-HF-180-M,,SIG)) 23260 53 8 Q0 value (ratio of resonance integral to thermal 23260 53 9 neutron activation cross-section) 23260 53 10 SAMPLE Provider - IRMM 23260 53 11 Matrix - Wire,Al alloy 23260 53 12 Average sample thickness h,mm - 1. 23260 53 13 -Elemental content, % weight - 5. 23260 53 14 -Elemental content, % weight - 0.1 23260 53 15 DECAY-DATA (72-HF-180-M,5.5HR,DG,93.3,0.171,DG,215.4,0.813, 23260 53 16 DG,332.3,0.941,DG,443.2,0.819,DG,500.7,0.143) 23260 53 17 METHOD Measurement at channels: 23260 53 18 1 S84 23260 53 19 2 Y4 23260 53 20 3 X26 23260 53 21 ANALYSIS The Q0 factors were determined by inputting the 23260 53 22 recommended Er value from references - 16.2 eV (+-12.%)23260 53 23 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 53 24 Uncertainty in the Q0 determination for for the simple 23260 53 25 case of one determination in one irradiation channel 23260 53 26 with one standard, given no type-B uncertainties 23260 53 27 contributions from the FCd = 1 and neutron 23260 53 28 self-shielding effects is on average 23260 53 29 2.5 % for foils, 2.6 % for compounds; 23260 53 30 include contributions from : 23260 53 31 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 53 32 for liquids/compounds in the parameter OMEGACd . 23260 53 33 - A combined type-B uncertainty from the comparator Qa 23260 53 34 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 53 35 S84 - 1.8 % . 23260 53 36 - A combined type-B uncertainty of 1.2 % during 23260 53 37 Qa -> Q0 conversion, due to the uncertainty on a and 23260 53 38 an average 7 % uncertainty on the recommended effective23260 53 39 resonance energy factor for the analyte, taken from 23260 53 40 references. 23260 53 41 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 53 42 Table 6 of J,JRN,302,631,2014. 23260 53 43 (COREL,23260056) Average Q0 . 23260 53 44 ENDBIB 42 0 23260 53 45 COMMON 2 3 23260 53 46 EN-MIN-NM EN-MEAN-DN 23260 53 47 EV EV 23260 53 48 0.5 0.0253 23260 53 49 ENDCOMMON 3 0 23260 53 50 DATA 6 1 23260 53 51 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 53 52 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 53 53 14.0 1. 14.6 3. 14.2 2. 23260 53 54 ENDDATA 3 0 23260 53 55 ENDSUBENT 54 0 23260 5399999 SUBENT 23260054 20141210 224123260 54 1 BIB 9 55 23260 54 2 REACTION 1((72-HF-180(N,G)72-HF-181,,RI)// 23260 54 3 (72-HF-180(N,G)72-HF-181,,SIG)) 23260 54 4 2((72-HF-180(N,G)72-HF-181,,RI)// 23260 54 5 (72-HF-180(N,G)72-HF-181,,SIG)) 23260 54 6 Q0 value (ratio of resonance integral to thermal 23260 54 7 neutron activation cross-section) 23260 54 8 SAMPLE Provider - IRMM 23260 54 9 Matrix - Wire,Al alloy 23260 54 10 Average sample thickness h,mm - 1. 23260 54 11 -Elemental content, % weight - 5. 23260 54 12 -Elemental content, % weight - 0.1 23260 54 13 DECAY-DATA (72-HF-181,42.39D,DG,133.0,0.433,DG,345.9,0.1512, 23260 54 14 DG,482.2,0.805) 23260 54 15 METHOD Measurement at channels: 23260 54 16 S84 23260 54 17 Y4 23260 54 18 X26 23260 54 19 ANALYSIS The Q0 factors were determined by 23260 54 20 approaches: 23260 54 21 1- the classical method: from the mean (AVG) and 23260 54 22 observed SD of the results from all channels employed, 23260 54 23 when inputting the recommended Er value from 23260 54 24 references - 115. eV (+-6.%) . 23260 54 25 2- the a-vector method applied on up to 3 irradiation 23260 54 26 channels: leading to simultaneous Q0 and Er 23260 54 27 determination. 23260 54 28 MISC-COL (MISC) Effective resonance energy Er defined by 23260 54 29 a-vector method. 23260 54 30 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 54 31 Uncertainty in the Q0 determination for for the simple 23260 54 32 case of one determination in one irradiation channel 23260 54 33 with one standard, given no type-B uncertainties 23260 54 34 contributions from the FCd = 1 and neutron 23260 54 35 self-shielding effects is on average 23260 54 36 2.5 % for foils, 2.6 % for compounds; 23260 54 37 include contributions from : 23260 54 38 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 54 39 for liquids/compounds in the parameter OMEGACd . 23260 54 40 - A combined type-B uncertainty from the comparator Qa 23260 54 41 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 54 42 S84 - 1.8 % . 23260 54 43 - A combined type-B uncertainty of 1.2 % during 23260 54 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 54 45 an average 7 % uncertainty on the recommended effective23260 54 46 resonance energy factor for the analyte, taken from 23260 54 47 references. 23260 54 48 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 54 49 E-gamma,keV k0, no-dim. 23260 54 50 133.0 2.33E-2 (+-1.7%) 23260 54 51 345.9 8.03E-3 (+-1.4%) 23260 54 52 482.2 4.31E-2 (+-1.3%) 23260 54 53 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 54 54 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 54 55 Table 6 of J,JRN,302,631,2014. 23260 54 56 1(DEP,23260059) Q0 measured at different channels. 23260 54 57 ENDBIB 55 0 23260 54 58 COMMON 2 3 23260 54 59 EN-MIN-NM EN-MEAN-DN 23260 54 60 EV EV 23260 54 61 0.5 0.0253 23260 54 62 ENDCOMMON 3 0 23260 54 63 DATA 6 1 23260 54 64 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 54 65 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 54 66 2.44 3. 2.46 2. 152. 8. 23260 54 67 ENDDATA 3 0 23260 54 68 ENDSUBENT 67 0 23260 5499999 SUBENT 23260055 20141210 224123260 55 1 BIB 7 42 23260 55 2 REACTION 1((72-HF-180(N,G)72-HF-181,,RI)// 23260 55 3 (72-HF-180(N,G)72-HF-181,,SIG)) 23260 55 4 2((72-HF-180(N,G)72-HF-181,,RI)// 23260 55 5 (72-HF-180(N,G)72-HF-181,,SIG)) 23260 55 6 3((72-HF-180(N,G)72-HF-181,,RI)// 23260 55 7 (72-HF-180(N,G)72-HF-181,,SIG)) 23260 55 8 Q0 value (ratio of resonance integral to thermal 23260 55 9 neutron activation cross-section) 23260 55 10 SAMPLE Provider - IRMM 23260 55 11 Matrix - Wire,Al alloy 23260 55 12 Average sample thickness h,mm - 1. 23260 55 13 -Elemental content, % weight - 5. 23260 55 14 -Elemental content, % weight - 0.1 23260 55 15 DECAY-DATA (72-HF-181,42.39D,DG,133.0,0.433,DG,345.9,0.1512, 23260 55 16 DG,482.2,0.805) 23260 55 17 METHOD Measurement at channels: 23260 55 18 1 S84 23260 55 19 2 Y4 23260 55 20 3 X26 23260 55 21 ANALYSIS The Q0 factors were determined by inputting the 23260 55 22 recommended Er value from references - 115. eV (+-6.%) 23260 55 23 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 55 24 Uncertainty in the Q0 determination for for the simple 23260 55 25 case of one determination in one irradiation channel 23260 55 26 with one standard, given no type-B uncertainties 23260 55 27 contributions from the FCd = 1 and neutron 23260 55 28 self-shielding effects is on average 23260 55 29 2.5 % for foils, 2.6 % for compounds; 23260 55 30 include contributions from : 23260 55 31 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 55 32 for liquids/compounds in the parameter OMEGACd . 23260 55 33 - A combined type-B uncertainty from the comparator Qa 23260 55 34 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 55 35 S84 - 1.8 % . 23260 55 36 - A combined type-B uncertainty of 1.2 % during 23260 55 37 Qa -> Q0 conversion, due to the uncertainty on a and 23260 55 38 an average 7 % uncertainty on the recommended effective23260 55 39 resonance energy factor for the analyte, taken from 23260 55 40 references. 23260 55 41 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 55 42 Table 6 of J,JRN,302,631,2014. 23260 55 43 (COREL,23260058) Average Q0 . 23260 55 44 ENDBIB 42 0 23260 55 45 COMMON 2 3 23260 55 46 EN-MIN-NM EN-MEAN-DN 23260 55 47 EV EV 23260 55 48 0.5 0.0253 23260 55 49 ENDCOMMON 3 0 23260 55 50 DATA 6 1 23260 55 51 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 55 52 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 55 53 2.45 2. 2.54 3. 2.36 3. 23260 55 54 ENDDATA 3 0 23260 55 55 ENDSUBENT 54 0 23260 5599999 SUBENT 23260056 20141210 224123260 56 1 BIB 9 83 23260 56 2 REACTION 1((73-TA-181(N,G)73-TA-182,,RI)// 23260 56 3 (73-TA-181(N,G)73-TA-182,,SIG)) 23260 56 4 2((73-TA-181(N,G)73-TA-182,,RI)// 23260 56 5 (73-TA-181(N,G)73-TA-182,,SIG)) 23260 56 6 Q0 value (ratio of resonance integral to thermal 23260 56 7 neutron activation cross-section) 23260 56 8 SAMPLE - Provider - IRMM 23260 56 9 Matrix - Foil 23260 56 10 Elemental content, % weight > 99.99 23260 56 11 Average sample thickness h,mm - 1. 23260 56 12 - Provider - IRMM 23260 56 13 Matrix - Foil, Y alloy 23260 56 14 Elemental content, % weight - 0.7 23260 56 15 Average sample thickness h,mm - 0.1 23260 56 16 - Provider - NIST 23260 56 17 Matrix - Liquid on paper 23260 56 18 Elemental content, % weight - 1. 23260 56 19 Average sample thickness h,mm - 1.25 23260 56 20 DECAY-DATA (73-TA-182-G,114.4D,DG,84.7,0.0265,DG,100.1,0.142, 23260 56 21 DG,113.7,0.0187,DG,152.4,0.0702,DG,156.4,0.0267, 23260 56 22 DG,179.4,0.0312,DG,198.4,0.0147,DG,222.1,0.0757, 23260 56 23 DG,229.3,0.0364,DG,264.1,0.0361,DG,1001.7,0.0209, 23260 56 24 DG,1121.3,0.3524,DG,1157.5,,DG,1189.1,0.1649, 23260 56 25 DG,1221.4,0.2723,DG,1231.0,0.1162,DG,1257.4,0.0151, 23260 56 26 DG,1289.2,0.0137) 23260 56 27 METHOD Measurement at channels: 23260 56 28 S84 23260 56 29 Y4 23260 56 30 X26 23260 56 31 ANALYSIS The Q0 factors were determined by 23260 56 32 approaches: 23260 56 33 1- the classical method: from the mean (AVG) and 23260 56 34 observed SD of the results from all channels employed, 23260 56 35 when inputting the recommended Er value from 23260 56 36 references - 10.4 eV (+-6.%) . 23260 56 37 2- the a-vector method applied on up to 3 irradiation 23260 56 38 channels: leading to simultaneous Q0 and Er 23260 56 39 determination. 23260 56 40 Cd transmission factor FCd=0.972 was used. 23260 56 41 MISC-COL (MISC) Effective resonance energy Er defined by 23260 56 42 a-vector method. 23260 56 43 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 56 44 Uncertainty in the Q0 determination for for the simple 23260 56 45 case of one determination in one irradiation channel 23260 56 46 with one standard, given no type-B uncertainties 23260 56 47 contributions from the FCd = 1 and neutron 23260 56 48 self-shielding effects is on average 23260 56 49 2.5 % for foils, 2.6 % for compounds; 23260 56 50 include contributions from : 23260 56 51 - The combined uncertainty of 1.5 % for foils and 1.2 %23260 56 52 for liquids/compounds in the parameter OMEGACd . 23260 56 53 - A combined type-B uncertainty from the comparator Qa 23260 56 54 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 56 55 S84 - 1.8 % . 23260 56 56 - A combined type-B uncertainty of 1.2 % during 23260 56 57 Qa -> Q0 conversion, due to the uncertainty on a and 23260 56 58 an average 7 % uncertainty on the recommended effective23260 56 59 resonance energy factor for the analyte, taken from 23260 56 60 references. 23260 56 61 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 56 62 E-gamma,keV k0, no-dim. 23260 56 63 84.7 6.23E-3 (+-1.3%) 23260 56 64 100.1 3.26E-2 (+-1.2%) 23260 56 65 113.7 4.38E-3 (+-1.2%) 23260 56 66 152.4 1.63E-2 (+-1.2%) 23260 56 67 156.4 6.26E-3 (+-1.2%) 23260 56 68 179.4 7.27E-3 (+-1.2%) 23260 56 69 198.4 3.40E-3 (+-1.2%) 23260 56 70 222.1 1.78E-2 (+-1.2%) 23260 56 71 229.3 8.56E-3 (+-1.2%) 23260 56 72 264.1 8.41E-3 (+-1.2%) 23260 56 73 1001.7 4.82E-3 (+-1.3%) 23260 56 74 1121.3 8.26E-2 (+-1.3%) 23260 56 75 1157.5 2.35E-3 (+-1.2%) 23260 56 76 1189.1 3.83E-2 (+-1.2%) 23260 56 77 1221.4 6.39E-2 (+-1.3%) 23260 56 78 1231.0 2.71E-2 (+-1.2%) 23260 56 79 1257.4 3.52E-3 (+-1.2%) 23260 56 80 1289.2 3.20E-3 (+-1.3%) 23260 56 81 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 56 82 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 56 83 Table 6 of J,JRN,302,631,2014. 23260 56 84 1(DEP,23260061) Q0 measured at different channels. 23260 56 85 ENDBIB 83 0 23260 56 86 COMMON 2 3 23260 56 87 EN-MIN-NM EN-MEAN-DN 23260 56 88 EV EV 23260 56 89 0.5 0.0253 23260 56 90 ENDCOMMON 3 0 23260 56 91 DATA 6 1 23260 56 92 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 56 93 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 56 94 37.0 3. 36.8 2. 11.1 15. 23260 56 95 ENDDATA 3 0 23260 56 96 ENDSUBENT 95 0 23260 5699999 SUBENT 23260057 20141210 224123260 57 1 BIB 7 54 23260 57 2 REACTION 1((73-TA-181(N,G)73-TA-182,,RI)// 23260 57 3 (73-TA-181(N,G)73-TA-182,,SIG)) 23260 57 4 2((73-TA-181(N,G)73-TA-182,,RI)// 23260 57 5 (73-TA-181(N,G)73-TA-182,,SIG)) 23260 57 6 3((73-TA-181(N,G)73-TA-182,,RI)// 23260 57 7 (73-TA-181(N,G)73-TA-182,,SIG)) 23260 57 8 Q0 value (ratio of resonance integral to thermal 23260 57 9 neutron activation cross-section) 23260 57 10 SAMPLE - Provider - IRMM 23260 57 11 Matrix - Foil 23260 57 12 Elemental content, % weight > 99.99 23260 57 13 Average sample thickness h,mm - 1. 23260 57 14 - Provider - IRMM 23260 57 15 Matrix - Foil, Y alloy 23260 57 16 Elemental content, % weight - 0.7 23260 57 17 Average sample thickness h,mm - 0.1 23260 57 18 - Provider - NIST 23260 57 19 Matrix - Liquid on paper 23260 57 20 Elemental content, % weight - 1. 23260 57 21 Average sample thickness h,mm - 1.25 23260 57 22 DECAY-DATA (73-TA-182-G,114.4D,DG,84.7,0.0265,DG,100.1,0.142, 23260 57 23 DG,113.7,0.0187,DG,152.4,0.0702,DG,156.4,0.0267, 23260 57 24 DG,179.4,0.0312,DG,198.4,0.0147,DG,222.1,0.0757, 23260 57 25 DG,229.3,0.0364,DG,264.1,0.0361,DG,1001.7,0.0209, 23260 57 26 DG,1121.3,0.3524,DG,1157.5,,DG,1189.1,0.1649, 23260 57 27 DG,1221.4,0.2723,DG,1231.0,0.1162,DG,1257.4,0.0151, 23260 57 28 DG,1289.2,0.0137) 23260 57 29 METHOD Measurement at channels: 23260 57 30 1 S84 23260 57 31 2 Y4 23260 57 32 3 X26 23260 57 33 ANALYSIS The Q0 factors were determined by inputting the 23260 57 34 recommended Er value from references - 10.4 eV (+-6.%) 23260 57 35 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 57 36 Uncertainty in the Q0 determination for for the simple 23260 57 37 case of one determination in one irradiation channel 23260 57 38 with one standard, given no type-B uncertainties 23260 57 39 contributions from the FCd = 1 and neutron 23260 57 40 self-shielding effects is on average 23260 57 41 2.5 % for foils, 2.6 % for compounds; 23260 57 42 include contributions from : 23260 57 43 - The combined uncertainty of 1.5 % for foils and 1.2 %23260 57 44 for liquids/compounds in the parameter OMEGACd . 23260 57 45 - A combined type-B uncertainty from the comparator Qa 23260 57 46 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 57 47 S84 - 1.8 % . 23260 57 48 - A combined type-B uncertainty of 1.2 % during 23260 57 49 Qa -> Q0 conversion, due to the uncertainty on a and 23260 57 50 an average 7 % uncertainty on the recommended effective23260 57 51 resonance energy factor for the analyte, taken from 23260 57 52 references. 23260 57 53 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 57 54 Table 6 of J,JRN,302,631,2014. 23260 57 55 (COREL,23260060) Average Q0 . 23260 57 56 ENDBIB 54 0 23260 57 57 COMMON 2 3 23260 57 58 EN-MIN-NM EN-MEAN-DN 23260 57 59 EV EV 23260 57 60 0.5 0.0253 23260 57 61 ENDCOMMON 3 0 23260 57 62 DATA 6 1 23260 57 63 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 57 64 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 57 65 36.5 4. 38.1 2. 36.0 5. 23260 57 66 ENDDATA 3 0 23260 57 67 ENDSUBENT 66 0 23260 5799999 SUBENT 23260058 20141210 224123260 58 1 BIB 9 57 23260 58 2 REACTION 1((78-PT-196(N,G)78-PT-197-M,,RI)// 23260 58 3 (78-PT-196(N,G)78-PT-197-M,,SIG)) 23260 58 4 2((78-PT-196(N,G)78-PT-197-M,,RI)// 23260 58 5 (78-PT-196(N,G)78-PT-197-M,,SIG)) 23260 58 6 Q0 value (ratio of resonance integral to thermal 23260 58 7 neutron activation cross-section) 23260 58 8 SAMPLE - Provider - Goodfellow 23260 58 9 Matrix - Wire 23260 58 10 Elemental content, % weight > 99.99 23260 58 11 Average sample thickness h,mm - 0.5 23260 58 12 - Provider - Alfa Aesar 23260 58 13 Matrix - Foil,Ru alloy 23260 58 14 Elemental content, % weight - 95.35 23260 58 15 Average sample thickness h,mm - 0.05 23260 58 16 - Provider - Alfa Aesar 23260 58 17 Matrix - Liquid on paper 23260 58 18 Elemental content, % weight - 0.1 23260 58 19 Average sample thickness h,mm - 1.25 23260 58 20 DECAY-DATA (78-PT-197-M,95.41MIN,DG,346.5,0.1110) 23260 58 21 METHOD Measurement at channels: 23260 58 22 S84 23260 58 23 X26 23260 58 24 ANALYSIS The Q0 factors were determined by 23260 58 25 approaches: 23260 58 26 1- the classical method: from the mean (AVG) and 23260 58 27 observed SD of the results from all channels employed, 23260 58 28 when inputting the recommended Er value from 23260 58 29 references - 291. eV . 23260 58 30 2- the a-vector method applied on up to 3 irradiation 23260 58 31 channels: leading to simultaneous Q0 and Er 23260 58 32 determination. 23260 58 33 MISC-COL (MISC) Effective resonance energy Er defined by 23260 58 34 a-vector method. 23260 58 35 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 58 36 Uncertainty in the Q0 determination for for the simple 23260 58 37 case of one determination in one irradiation channel 23260 58 38 with one standard, given no type-B uncertainties 23260 58 39 contributions from the FCd = 1 and neutron 23260 58 40 self-shielding effects is on average 23260 58 41 2.5 % for foils, 2.6 % for compounds; 23260 58 42 include contributions from : 23260 58 43 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 58 44 for liquids/compounds in the parameter OMEGACd . 23260 58 45 - A combined type-B uncertainty from the comparator Qa 23260 58 46 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 58 47 - A combined type-B uncertainty of 1.2 % during 23260 58 48 Qa -> Q0 conversion, due to the uncertainty on a and 23260 58 49 an average 7 % uncertainty on the recommended effective23260 58 50 resonance energy factor for the analyte, taken from 23260 58 51 references. 23260 58 52 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 58 53 E-gamma,keV k0, no-dim. 23260 58 54 346.5 1.06E-5 (+-1.1%) 23260 58 55 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 58 56 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 58 57 Table 6 of J,JRN,302,631,2014. 23260 58 58 1(DEP,23260063) Q0 measured at different channels. 23260 58 59 ENDBIB 57 0 23260 58 60 COMMON 2 3 23260 58 61 EN-MIN-NM EN-MEAN-DN 23260 58 62 EV EV 23260 58 63 0.5 0.0253 23260 58 64 ENDCOMMON 3 0 23260 58 65 DATA 6 1 23260 58 66 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 58 67 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 58 68 8.44 15. 9.62 4. 5319. 5. 23260 58 69 ENDDATA 3 0 23260 58 70 ENDSUBENT 69 0 23260 5899999 SUBENT 23260059 20141210 224123260 59 1 BIB 7 44 23260 59 2 REACTION 1((78-PT-196(N,G)78-PT-197-M,,RI)// 23260 59 3 (78-PT-196(N,G)78-PT-197-M,,SIG)) 23260 59 4 2((78-PT-196(N,G)78-PT-197-M,,RI)// 23260 59 5 (78-PT-196(N,G)78-PT-197-M,,SIG)) 23260 59 6 Q0 value (ratio of resonance integral to thermal 23260 59 7 neutron activation cross-section) 23260 59 8 SAMPLE - Provider - Goodfellow 23260 59 9 Matrix - Wire 23260 59 10 Elemental content, % weight > 99.99 23260 59 11 Average sample thickness h,mm - 0.5 23260 59 12 - Provider - Alfa Aesar 23260 59 13 Matrix - Foil,Ru alloy 23260 59 14 Elemental content, % weight - 95.35 23260 59 15 Average sample thickness h,mm - 0.05 23260 59 16 - Provider - Alfa Aesar 23260 59 17 Matrix - Liquid on paper 23260 59 18 Elemental content, % weight - 0.1 23260 59 19 Average sample thickness h,mm - 1.25 23260 59 20 DECAY-DATA (78-PT-197-M,95.41MIN,DG,346.5,0.1110) 23260 59 21 METHOD Measurement at channels: 23260 59 22 1 S84 23260 59 23 2 X26 23260 59 24 ANALYSIS The Q0 factors were determined by inputting the 23260 59 25 recommended Er value from references - 291. eV . 23260 59 26 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 59 27 Uncertainty in the Q0 determination for for the simple 23260 59 28 case of one determination in one irradiation channel 23260 59 29 with one standard, given no type-B uncertainties 23260 59 30 contributions from the FCd = 1 and neutron 23260 59 31 self-shielding effects is on average 23260 59 32 2.5 % for foils, 2.6 % for compounds; 23260 59 33 include contributions from : 23260 59 34 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 59 35 for liquids/compounds in the parameter OMEGACd . 23260 59 36 - A combined type-B uncertainty from the comparator Qa 23260 59 37 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 59 38 - A combined type-B uncertainty of 1.2 % during 23260 59 39 Qa -> Q0 conversion, due to the uncertainty on a and 23260 59 40 an average 7 % uncertainty on the recommended effective23260 59 41 resonance energy factor for the analyte, taken from 23260 59 42 references. 23260 59 43 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 59 44 Table 6 of J,JRN,302,631,2014. 23260 59 45 (COREL,23260062) Average Q0 . 23260 59 46 ENDBIB 44 0 23260 59 47 COMMON 2 3 23260 59 48 EN-MIN-NM EN-MEAN-DN 23260 59 49 EV EV 23260 59 50 0.5 0.0253 23260 59 51 ENDCOMMON 3 0 23260 59 52 DATA 4 1 23260 59 53 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23260 59 54 NO-DIM PER-CENT NO-DIM PER-CENT 23260 59 55 9.71 3. 7.16 2. 23260 59 56 ENDDATA 3 0 23260 59 57 ENDSUBENT 56 0 23260 5999999 SUBENT 23260060 20141210 224123260 60 1 BIB 9 59 23260 60 2 REACTION 1((78-PT-196(N,G)78-PT-197,,RI)// 23260 60 3 (78-PT-196(N,G)78-PT-197,,SIG)) 23260 60 4 2((78-PT-196(N,G)78-PT-197,,RI)// 23260 60 5 (78-PT-196(N,G)78-PT-197,,SIG)) 23260 60 6 Q0 value (ratio of resonance integral to thermal 23260 60 7 neutron activation cross-section) 23260 60 8 SAMPLE - Provider - Goodfellow 23260 60 9 Matrix - Wire 23260 60 10 Elemental content, % weight > 99.99 23260 60 11 Average sample thickness h,mm - 0.5 23260 60 12 - Provider - Alfa Aesar 23260 60 13 Matrix - Foil,Ru alloy 23260 60 14 Elemental content, % weight - 95.35 23260 60 15 Average sample thickness h,mm - 0.05 23260 60 16 - Provider - Alfa Aesar 23260 60 17 Matrix - Liquid on paper 23260 60 18 Elemental content, % weight - 0.1 23260 60 19 Average sample thickness h,mm - 1.25 23260 60 20 DECAY-DATA (78-PT-197-G,19.892HR,DG,191.4,0.0370,DG,268.8,0.0023) 23260 60 21 METHOD Measurement at channels: 23260 60 22 S84 23260 60 23 Y4 23260 60 24 X26 23260 60 25 ANALYSIS The Q0 factors were determined by 23260 60 26 approaches: 23260 60 27 1- the classical method: from the mean (AVG) and 23260 60 28 observed SD of the results from all channels employed, 23260 60 29 when inputting the recommended Er value from 23260 60 30 references - 291. eV . 23260 60 31 2- the a-vector method applied on up to 3 irradiation 23260 60 32 channels: leading to simultaneous Q0 and Er 23260 60 33 determination. 23260 60 34 MISC-COL (MISC) Effective resonance energy Er defined by 23260 60 35 a-vector method. 23260 60 36 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 60 37 Uncertainty in the Q0 determination for for the simple 23260 60 38 case of one determination in one irradiation channel 23260 60 39 with one standard, given no type-B uncertainties 23260 60 40 contributions from the FCd = 1 and neutron 23260 60 41 self-shielding effects is on average 23260 60 42 2.5 % for foils, 2.6 % for compounds; 23260 60 43 include contributions from : 23260 60 44 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 60 45 for liquids/compounds in the parameter OMEGACd . 23260 60 46 - A combined type-B uncertainty from the comparator Qa 23260 60 47 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 60 48 - A combined type-B uncertainty of 1.2 % during 23260 60 49 Qa -> Q0 conversion, due to the uncertainty on a and 23260 60 50 an average 7 % uncertainty on the recommended effective23260 60 51 resonance energy factor for the analyte, taken from 23260 60 52 references. 23260 60 53 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 60 54 E-gamma,keV k0, no-dim. 23260 60 55 191.4 7.51E-5 (+-1.5%) 23260 60 56 268.8 4.67E-6 (+-1.4) 23260 60 57 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 60 58 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 60 59 Table 6 of J,JRN,302,631,2014. 23260 60 60 1(DEP,23260065) Q0 measured at different channels. 23260 60 61 ENDBIB 59 0 23260 60 62 COMMON 2 3 23260 60 63 EN-MIN-NM EN-MEAN-DN 23260 60 64 EV EV 23260 60 65 0.5 0.0253 23260 60 66 ENDCOMMON 3 0 23260 60 67 DATA 6 1 23260 60 68 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 60 69 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 60 70 8.17 12. 9.57 4. 5319. 5. 23260 60 71 ENDDATA 3 0 23260 60 72 ENDSUBENT 71 0 23260 6099999 SUBENT 23260061 20141210 224123260 61 1 BIB 7 47 23260 61 2 REACTION 1((78-PT-196(N,G)78-PT-197,,RI)// 23260 61 3 (78-PT-196(N,G)78-PT-197,,SIG)) 23260 61 4 2((78-PT-196(N,G)78-PT-197,,RI)// 23260 61 5 (78-PT-196(N,G)78-PT-197,,SIG)) 23260 61 6 3((78-PT-196(N,G)78-PT-197,,RI)// 23260 61 7 (78-PT-196(N,G)78-PT-197,,SIG)) 23260 61 8 Q0 value (ratio of resonance integral to thermal 23260 61 9 neutron activation cross-section) 23260 61 10 SAMPLE - Provider - Goodfellow 23260 61 11 Matrix - Wire 23260 61 12 Elemental content, % weight > 99.99 23260 61 13 Average sample thickness h,mm - 0.5 23260 61 14 - Provider - Alfa Aesar 23260 61 15 Matrix - Foil,Ru alloy 23260 61 16 Elemental content, % weight - 95.35 23260 61 17 Average sample thickness h,mm - 0.05 23260 61 18 - Provider - Alfa Aesar 23260 61 19 Matrix - Liquid on paper 23260 61 20 Elemental content, % weight - 0.1 23260 61 21 Average sample thickness h,mm - 1.25 23260 61 22 DECAY-DATA (78-PT-197-G,19.892HR,DG,191.4,0.0370,DG,268.8,0.0023) 23260 61 23 METHOD Measurement at channels: 23260 61 24 1 S84 23260 61 25 2 Y4 23260 61 26 3 X26 23260 61 27 ANALYSIS The Q0 factors were determined by inputting the 23260 61 28 recommended Er value from references - 291. eV . 23260 61 29 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 61 30 Uncertainty in the Q0 determination for for the simple 23260 61 31 case of one determination in one irradiation channel 23260 61 32 with one standard, given no type-B uncertainties 23260 61 33 contributions from the FCd = 1 and neutron 23260 61 34 self-shielding effects is on average 23260 61 35 2.5 % for foils, 2.6 % for compounds; 23260 61 36 include contributions from : 23260 61 37 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 61 38 for liquids/compounds in the parameter OMEGACd . 23260 61 39 - A combined type-B uncertainty from the comparator Qa 23260 61 40 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 61 41 - A combined type-B uncertainty of 1.2 % during 23260 61 42 Qa -> Q0 conversion, due to the uncertainty on a and 23260 61 43 an average 7 % uncertainty on the recommended effective23260 61 44 resonance energy factor for the analyte, taken from 23260 61 45 references. 23260 61 46 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 61 47 Table 6 of J,JRN,302,631,2014. 23260 61 48 (COREL,23260064) Average Q0 . 23260 61 49 ENDBIB 47 0 23260 61 50 COMMON 2 3 23260 61 51 EN-MIN-NM EN-MEAN-DN 23260 61 52 EV EV 23260 61 53 0.5 0.0253 23260 61 54 ENDCOMMON 3 0 23260 61 55 DATA 6 1 23260 61 56 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 61 57 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 61 58 9.55 3. 7.98 2. 6.97 2. 23260 61 59 ENDDATA 3 0 23260 61 60 ENDSUBENT 59 0 23260 6199999 SUBENT 23260062 20141210 224123260 62 1 BIB 9 64 23260 62 2 REACTION 1((78-PT-198(N,G)78-PT-199,,RI)// 23260 62 3 (78-PT-198(N,G)78-PT-199,,SIG)) 23260 62 4 2((78-PT-198(N,G)78-PT-199,,RI)// 23260 62 5 (78-PT-198(N,G)78-PT-199,,SIG)) 23260 62 6 Q0 value (ratio of resonance integral to thermal 23260 62 7 neutron activation cross-section) 23260 62 8 SAMPLE - Provider - Goodfellow 23260 62 9 Matrix - Wire 23260 62 10 Elemental content, % weight > 99.99 23260 62 11 Average sample thickness h,mm - 0.5 23260 62 12 - Provider - Alfa Aesar 23260 62 13 Matrix - Foil,Ru alloy 23260 62 14 Elemental content, % weight - 95.35 23260 62 15 Average sample thickness h,mm - 0.05 23260 62 16 - Provider - Alfa Aesar 23260 62 17 Matrix - Liquid on paper 23260 62 18 Elemental content, % weight - 0.1 23260 62 19 Average sample thickness h,mm - 1.25 23260 62 20 DECAY-DATA (78-PT-199-G,30.8MIN,DG,493.8,0.0447,DG,543.0,0.1174, 23260 62 21 DG,714.6,0.0145) 23260 62 22 (79-AU-199,3.139D,DG,158.4,0.400,DG,208.2,0.0872) 23260 62 23 METHOD Measurement at channels: 23260 62 24 S84 23260 62 25 Y4 23260 62 26 X26 23260 62 27 ANALYSIS The Q0 factors were determined by 23260 62 28 approaches: 23260 62 29 1- the classical method: from the mean (AVG) and 23260 62 30 observed SD of the results from all channels employed, 23260 62 31 when inputting the recommended Er value from 23260 62 32 references - 106. eV (+-3.) . 23260 62 33 2- the a-vector method applied on up to 3 irradiation 23260 62 34 channels: leading to simultaneous Q0 and Er 23260 62 35 determination. 23260 62 36 MISC-COL (MISC) Effective resonance energy Er defined by 23260 62 37 a-vector method. 23260 62 38 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 62 39 Uncertainty in the Q0 determination for for the simple 23260 62 40 case of one determination in one irradiation channel 23260 62 41 with one standard, given no type-B uncertainties 23260 62 42 contributions from the FCd = 1 and neutron 23260 62 43 self-shielding effects is on average 23260 62 44 2.5 % for foils, 2.6 % for compounds; 23260 62 45 include contributions from : 23260 62 46 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 62 47 for liquids/compounds in the parameter OMEGACd . 23260 62 48 - A combined type-B uncertainty from the comparator Qa 23260 62 49 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 62 50 - A combined type-B uncertainty of 1.2 % during 23260 62 51 Qa -> Q0 conversion, due to the uncertainty on a and 23260 62 52 an average 7 % uncertainty on the recommended effective23260 62 53 resonance energy factor for the analyte, taken from 23260 62 54 references. 23260 62 55 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 62 56 E-gamma,keV k0, no-dim. 23260 62 57 493.8 1.15E-4 (+-1.0%) 23260 62 58 543.0 3.00E-4 (+-1.0%) 23260 62 59 714.6 3.72E-5 (+-1.0%) 23260 62 60 158.4 1.04E-3 (+-1.1%) 23260 62 61 208.2 2.26E-4 (+-1.0%) 23260 62 62 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 62 63 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 62 64 Table 6 of J,JRN,302,631,2014. 23260 62 65 1(DEP,23260067) Q0 measured at different channels. 23260 62 66 ENDBIB 64 0 23260 62 67 COMMON 2 3 23260 62 68 EN-MIN-NM EN-MEAN-DN 23260 62 69 EV EV 23260 62 70 0.5 0.0253 23260 62 71 ENDCOMMON 3 0 23260 62 72 DATA 6 1 23260 62 73 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 62 74 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 62 75 16.9 2. 17.0 2. 114. 8. 23260 62 76 ENDDATA 3 0 23260 62 77 ENDSUBENT 76 0 23260 6299999 SUBENT 23260063 20141210 224123260 63 1 BIB 7 49 23260 63 2 REACTION 1((78-PT-198(N,G)78-PT-199,,RI)// 23260 63 3 (78-PT-198(N,G)78-PT-199,,SIG)) 23260 63 4 2((78-PT-198(N,G)78-PT-199,,RI)// 23260 63 5 (78-PT-198(N,G)78-PT-199,,SIG)) 23260 63 6 3((78-PT-198(N,G)78-PT-199,,RI)// 23260 63 7 (78-PT-198(N,G)78-PT-199,,SIG)) 23260 63 8 Q0 value (ratio of resonance integral to thermal 23260 63 9 neutron activation cross-section) 23260 63 10 SAMPLE - Provider - Goodfellow 23260 63 11 Matrix - Wire 23260 63 12 Elemental content, % weight > 99.99 23260 63 13 Average sample thickness h,mm - 0.5 23260 63 14 - Provider - Alfa Aesar 23260 63 15 Matrix - Foil,Ru alloy 23260 63 16 Elemental content, % weight - 95.35 23260 63 17 Average sample thickness h,mm - 0.05 23260 63 18 - Provider - Alfa Aesar 23260 63 19 Matrix - Liquid on paper 23260 63 20 Elemental content, % weight - 0.1 23260 63 21 Average sample thickness h,mm - 1.25 23260 63 22 DECAY-DATA (78-PT-199-G,30.8MIN,DG,493.8,0.0447,DG,543.0,0.1174, 23260 63 23 DG,714.6,0.0145) 23260 63 24 (79-AU-199,3.139D,DG,158.4,0.400,DG,208.2,0.0872) 23260 63 25 METHOD Measurement at channels: 23260 63 26 1 S84 23260 63 27 2 Y4 23260 63 28 3 X26 23260 63 29 ANALYSIS The Q0 factors were determined by inputting the 23260 63 30 recommended Er value from references - 106. eV (+-3.) .23260 63 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 63 32 Uncertainty in the Q0 determination for for the simple 23260 63 33 case of one determination in one irradiation channel 23260 63 34 with one standard, given no type-B uncertainties 23260 63 35 contributions from the FCd = 1 and neutron 23260 63 36 self-shielding effects is on average 23260 63 37 2.5 % for foils, 2.6 % for compounds; 23260 63 38 include contributions from : 23260 63 39 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 63 40 for liquids/compounds in the parameter OMEGACd . 23260 63 41 - A combined type-B uncertainty from the comparator Qa 23260 63 42 factor for channels X26 up to 2.1 %, S84 - 1.8 % . 23260 63 43 - A combined type-B uncertainty of 1.2 % during 23260 63 44 Qa -> Q0 conversion, due to the uncertainty on a and 23260 63 45 an average 7 % uncertainty on the recommended effective23260 63 46 resonance energy factor for the analyte, taken from 23260 63 47 references. 23260 63 48 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 63 49 Table 6 of J,JRN,302,631,2014. 23260 63 50 (COREL,23260066) Average Q0 . 23260 63 51 ENDBIB 49 0 23260 63 52 COMMON 2 3 23260 63 53 EN-MIN-NM EN-MEAN-DN 23260 63 54 EV EV 23260 63 55 0.5 0.0253 23260 63 56 ENDCOMMON 3 0 23260 63 57 DATA 6 1 23260 63 58 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 63 59 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 63 60 16.7 2. 17.1 2. 16.7 3. 23260 63 61 ENDDATA 3 0 23260 63 62 ENDSUBENT 61 0 23260 6399999 SUBENT 23260064 20141210 224123260 64 1 BIB 9 59 23260 64 2 REACTION 1((90-TH-232(N,G)90-TH-233,,RI)// 23260 64 3 (90-TH-232(N,G)90-TH-233,,SIG)) 23260 64 4 2((90-TH-232(N,G)90-TH-233,,RI)// 23260 64 5 (90-TH-232(N,G)90-TH-233,,SIG)) 23260 64 6 Q0 value (ratio of resonance integral to thermal 23260 64 7 neutron activation cross-section) 23260 64 8 SAMPLE - Provider - IRMM 23260 64 9 Matrix - Wire, Al alloy 23260 64 10 Elemental content, % weight - 0.819 23260 64 11 Average sample thickness h,mm - 1. 23260 64 12 DECAY-DATA (90-TH-233,22.3MIN) 23260 64 13 (91-PA-233,26.97D,DG,300.1,0.0663,DG,311.9,0.385, 23260 64 14 DG,340.5,0.0445,DG,375.4,0.00679,DG,398.5,0.01391, 23260 64 15 DG,415.8,0.0173) 23260 64 16 METHOD Measurement at channels: 23260 64 17 S84 23260 64 18 Y4 23260 64 19 X26 23260 64 20 ANALYSIS The Q0 factors were determined by 23260 64 21 approaches: 23260 64 22 1- the classical method: from the mean (AVG) and 23260 64 23 observed SD of the results from all channels employed, 23260 64 24 when inputting the recommended Er value from 23260 64 25 references - 54.4 eV (+-1.) . 23260 64 26 2- the a-vector method applied on up to 3 irradiation 23260 64 27 channels: leading to simultaneous Q0 and Er 23260 64 28 determination. 23260 64 29 MISC-COL (MISC) Effective resonance energy Er defined by 23260 64 30 a-vector method. 23260 64 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 64 32 Uncertainty in the Q0 determination for for the simple 23260 64 33 case of one determination in one irradiation channel 23260 64 34 with one standard, given no type-B uncertainties 23260 64 35 contributions from the FCd = 1 and neutron 23260 64 36 self-shielding effects is on average 23260 64 37 2.5 % for foils, 2.6 % for compounds; 23260 64 38 include contributions from : 23260 64 39 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 64 40 for liquids/compounds in the parameter OMEGACd . 23260 64 41 - A combined type-B uncertainty from the comparator Qa 23260 64 42 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 64 43 S84 - 1.8 % . 23260 64 44 - A combined type-B uncertainty of 1.2 % during 23260 64 45 Qa -> Q0 conversion, due to the uncertainty on a and 23260 64 46 an average 7 % uncertainty on the recommended effective23260 64 47 resonance energy factor for the analyte, taken from 23260 64 48 references. 23260 64 49 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 64 50 E-gamma,keV k0, no-dim. 23260 64 51 300.1 4.42E-3 (+-1.7%) 23260 64 52 311.9 2.57E-2 (+-1.7%) 23260 64 53 340.5 2.98E-3 (+-1.7%) 23260 64 54 375.4 4.51E-4 (+-1.7%) 23260 64 55 398.5 9.29E-4 (+-1.8%) 23260 64 56 415.8 1.15E-3 (+-1.8%) 23260 64 57 STATUS (TABLE) Table 5 of J,JRN,302,655,2014; 23260 64 58 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 64 59 Table 6 of J,JRN,302,631,2014. 23260 64 60 1(DEP,23260069) Q0 measured at different channels. 23260 64 61 ENDBIB 59 0 23260 64 62 COMMON 2 3 23260 64 63 EN-MIN-NM EN-MEAN-DN 23260 64 64 EV EV 23260 64 65 0.5 0.0253 23260 64 66 ENDCOMMON 3 0 23260 64 67 DATA 6 1 23260 64 68 DATA 1DATA-ERR 1DATA 2DATA-ERR 2MISC MISC-ERR 23260 64 69 NO-DIM PER-CENT NO-DIM PER-CENT EV PER-CENT 23260 64 70 11.8 2. 11.7 2. 51.7 1. 23260 64 71 ENDDATA 3 0 23260 64 72 ENDSUBENT 71 0 23260 6499999 SUBENT 23260065 20141210 224123260 65 1 BIB 7 43 23260 65 2 REACTION 1((90-TH-232(N,G)90-TH-233,,RI)// 23260 65 3 (90-TH-232(N,G)90-TH-233,,SIG)) 23260 65 4 2((90-TH-232(N,G)90-TH-233,,RI)// 23260 65 5 (90-TH-232(N,G)90-TH-233,,SIG)) 23260 65 6 3((90-TH-232(N,G)90-TH-233,,RI)// 23260 65 7 (90-TH-232(N,G)90-TH-233,,SIG)) 23260 65 8 Q0 value (ratio of resonance integral to thermal 23260 65 9 neutron activation cross-section) 23260 65 10 SAMPLE - Provider - IRMM 23260 65 11 Matrix - Wire, Al alloy 23260 65 12 Elemental content, % weight - 0.819 23260 65 13 Average sample thickness h,mm - 1. 23260 65 14 DECAY-DATA (90-TH-233,22.3MIN) 23260 65 15 (91-PA-233,26.97D,DG,300.1,0.0663,DG,311.9,0.385, 23260 65 16 DG,340.5,0.0445,DG,375.4,0.00679,DG,398.5,0.01391, 23260 65 17 DG,415.8,0.0173) 23260 65 18 METHOD Measurement at channels: 23260 65 19 1 S84 23260 65 20 2 Y4 23260 65 21 3 X26 23260 65 22 ANALYSIS The Q0 factors were determined by inputting the 23260 65 23 recommended Er value from references - 54.4 eV (+-1.) .23260 65 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 65 25 Uncertainty in the Q0 determination for for the simple 23260 65 26 case of one determination in one irradiation channel 23260 65 27 with one standard, given no type-B uncertainties 23260 65 28 contributions from the FCd = 1 and neutron 23260 65 29 self-shielding effects is on average 23260 65 30 2.5 % for foils, 2.6 % for compounds; 23260 65 31 include contributions from : 23260 65 32 - The combined uncertainty of 1.1 % for foils and 1.2 %23260 65 33 for liquids/compounds in the parameter OMEGACd . 23260 65 34 - A combined type-B uncertainty from the comparator Qa 23260 65 35 factor for channels X26 up to 2.1 %, Y4 - 1.9 % , 23260 65 36 S84 - 1.8 % . 23260 65 37 - A combined type-B uncertainty of 1.2 % during 23260 65 38 Qa -> Q0 conversion, due to the uncertainty on a and 23260 65 39 an average 7 % uncertainty on the recommended effective23260 65 40 resonance energy factor for the analyte, taken from 23260 65 41 references. 23260 65 42 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 65 43 Table 6 of J,JRN,302,631,2014. 23260 65 44 (COREL,23260068) Average Q0. 23260 65 45 ENDBIB 43 0 23260 65 46 COMMON 2 3 23260 65 47 EN-MIN-NM EN-MEAN-DN 23260 65 48 EV EV 23260 65 49 0.5 0.0253 23260 65 50 ENDCOMMON 3 0 23260 65 51 DATA 6 1 23260 65 52 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260 65 53 NO-DIM PER-CENT NO-DIM PER-CENT NO-DIM PER-CENT 23260 65 54 11.8 4. 11.8 3. 11.8 2. 23260 65 55 ENDDATA 3 0 23260 65 56 ENDSUBENT 55 0 23260 6599999 SUBENT 23260066 20141210 224123260 66 1 BIB 4 9 23260 66 2 REACTION (19-K-41(N,G)19-K-42,,SIG) 23260 66 3 SIG-0 - the neutron capture cross-section 23260 66 4 for neutrons at an average energy of E0=25.3 meV 23260 66 5 or velocity v0=2200 m/s. 23260 66 6 ANALYSIS Derived from directly measured data. 23260 66 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 66 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 66 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 66 10 (DEP,23260067) Directly measured data. 23260 66 11 ENDBIB 9 0 23260 66 12 COMMON 1 3 23260 66 13 EN 23260 66 14 EV 23260 66 15 0.0253 23260 66 16 ENDCOMMON 3 0 23260 66 17 DATA 2 1 23260 66 18 DATA DATA-ERR 23260 66 19 B B 23260 66 20 1.451 0.003 23260 66 21 ENDDATA 3 0 23260 66 22 ENDSUBENT 21 0 23260 6699999 SUBENT 23260067 20141210 224123260 67 1 BIB 7 20 23260 67 2 REACTION (19-K-41(N,G)19-K-42,,SIG) 23260 67 3 Effective thermal neutron cross-section. 23260 67 4 SAMPLE Provider - Alfa Aesar, 23260 67 5 Matrix - Liquid on paper, 23260 67 6 Elemental content, % weight - 0.1 23260 67 7 Average sample thickness h,mm - 1.25 23260 67 8 (19-K-41,NAT=0.067302) 6.7302(44) %. 23260 67 9 DECAY-DATA ((1.)19-K-42,12.36HR,DG,312.7,0.00336) 23260 67 10 ((2.)19-K-42,12.36HR,DG,1524.7,0.1808) 23260 67 11 METHOD Y4 channel. 4 samples x 2 irradiation. 23260 67 12 ANALYSIS An effective thermal neutron cross-section SIG was 23260 67 13 extrapolated with aid of the k0-definition, atomic 23260 67 14 weight, isotopic composition, the gamma intensities 23260 67 15 values. 23260 67 16 Defined according to their ADS(activation decay scheme,23260 67 17 including decay branching factors). 23260 67 18 ERR-ANALYS Not given. 23260 67 19 Uncertainty on exp. SIG value comes from to the obs. SD23260 67 20 between all available gamma-lines. 23260 67 21 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 67 22 ENDBIB 20 0 23260 67 23 COMMON 1 3 23260 67 24 EN-MEAN 23260 67 25 EV 23260 67 26 0.0253 23260 67 27 ENDCOMMON 3 0 23260 67 28 DATA 2 2 23260 67 29 DATA DECAY-FLAG 23260 67 30 B NO-DIM 23260 67 31 1.449 1. 23260 67 32 1.453 2. 23260 67 33 ENDDATA 4 0 23260 67 34 ENDSUBENT 33 0 23260 6799999 SUBENT 23260068 20141210 224123260 68 1 BIB 4 9 23260 68 2 REACTION (24-CR-50(N,G)24-CR-51,,SIG) 23260 68 3 SIG-0 - the neutron capture cross-section 23260 68 4 for neutrons at an average energy of E0=25.3 meV 23260 68 5 or velocity v0=2200 m/s. 23260 68 6 ANALYSIS Derived from directly measured data. 23260 68 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 68 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 68 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 68 10 (DEP,23260069) Directly measured data. 23260 68 11 ENDBIB 9 0 23260 68 12 COMMON 1 3 23260 68 13 EN 23260 68 14 EV 23260 68 15 0.0253 23260 68 16 ENDCOMMON 3 0 23260 68 17 DATA 2 1 23260 68 18 DATA DATA-ERR 23260 68 19 B B 23260 68 20 14.41 0.13 23260 68 21 ENDDATA 3 0 23260 68 22 ENDSUBENT 21 0 23260 6899999 SUBENT 23260069 20141210 224123260 69 1 BIB 7 22 23260 69 2 REACTION (24-CR-50(N,G)24-CR-51,,SIG) 23260 69 3 Effective thermal neutron cross-section. 23260 69 4 SAMPLE Provider - Goodfellow IRMM 23260 69 5 Matrix - Slab Foil,Al Alloy23260 69 6 Elemental content, % weight > 99.99 10. 23260 69 7 Average sample thickness h,mm - 0.05 0.8 23260 69 8 (24-CR-50,NAT=0.04345) 4.345(13) % . 23260 69 9 DECAY-DATA (24-CR-51,27.7D,DG,320.1,0.0991) 23260 69 10 METHOD Measurements at channels S84, Y4 - 23260 69 11 5 samples from IRMM in 2 irrad.; 23260 69 12 10 samples from GF in 3 irrad. 23260 69 13 ANALYSIS Derived from directly measured data. 23260 69 14 An effective thermal neutron cross-section SIG was 23260 69 15 extrapolated with aid of the k0-definition, atomic 23260 69 16 weight, isotopic composition, the gamma intensities 23260 69 17 values. 23260 69 18 Defined according to their ADS(activation decay scheme,23260 69 19 including decay branching factors). 23260 69 20 ERR-ANALYS Uncertainty is not given. 23260 69 21 Uncertainty on exp. SIG value comes from to the obs. SD23260 69 22 between all available gamma-lines. 23260 69 23 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 69 24 ENDBIB 22 0 23260 69 25 COMMON 1 3 23260 69 26 EN-MEAN 23260 69 27 EV 23260 69 28 0.0253 23260 69 29 ENDCOMMON 3 0 23260 69 30 DATA 1 1 23260 69 31 DATA 23260 69 32 B 23260 69 33 14.41 23260 69 34 ENDDATA 3 0 23260 69 35 ENDSUBENT 34 0 23260 6999999 SUBENT 23260070 20141210 224123260 70 1 BIB 5 10 23260 70 2 REACTION (38-SR-84(N,G)38-SR-85-M,,SIG) 23260 70 3 SIG-0 - the neutron capture cross-section 23260 70 4 for neutrons at an average energy of E0=25.3 meV 23260 70 5 or velocity v0=2200 m/s. 23260 70 6 DECAY-DATA (38-SR-85-M,67.63MIN) 23260 70 7 ANALYSIS Derived from directly measured data. 23260 70 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 70 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 70 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 70 11 (DEP,23260071) Directly measured data. 23260 70 12 ENDBIB 10 0 23260 70 13 COMMON 1 3 23260 70 14 EN 23260 70 15 EV 23260 70 16 0.0253 23260 70 17 ENDCOMMON 3 0 23260 70 18 DATA 2 1 23260 70 19 DATA DATA-ERR 23260 70 20 B B 23260 70 21 0.659 0.003 23260 70 22 ENDDATA 3 0 23260 70 23 ENDSUBENT 22 0 23260 7099999 SUBENT 23260071 20141210 224123260 71 1 BIB 7 22 23260 71 2 REACTION (38-SR-84(N,G)38-SR-85-M,,SIG) 23260 71 3 Effective thermal neutron cross-section. 23260 71 4 SAMPLE - Provider - Sigma-Aldrich 23260 71 5 Matrix - SrCO(3) 23260 71 6 Elemental content, % weight - 59.351 23260 71 7 - Average sample thickness h,mm - 0.2 23260 71 8 - Average sample thickness h,mm - 0.6 23260 71 9 (38-SR-54,NAT=0.0056) 0.56+-0.01 % 23260 71 10 DECAY-DATA ((1.)38-SR-85-M,67.63MIN,DG,151.2,0.123) 23260 71 11 ((2.)38-SR-85-M,67.63MIN,DG,231.9,0.841) 23260 71 12 METHOD Measurements at channel S84: 2 samples x 5 irradiation,23260 71 13 Cavity : 4 samples x 2 irradiation. 23260 71 14 ANALYSIS An effective thermal neutron cross-section SIG was 23260 71 15 extrapolated with aid of the k0-definition, atomic 23260 71 16 weight, isotopic composition, the gamma intensities 23260 71 17 values. 23260 71 18 Defined according to their ADS(activation decay scheme,23260 71 19 including decay branching factors). 23260 71 20 ERR-ANALYS Not given. 23260 71 21 Uncertainty on exp. SIG value comes from to the obs. SD23260 71 22 between all available gamma-lines. 23260 71 23 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 71 24 ENDBIB 22 0 23260 71 25 COMMON 1 3 23260 71 26 EN-MEAN 23260 71 27 EV 23260 71 28 0.0253 23260 71 29 ENDCOMMON 3 0 23260 71 30 DATA 2 2 23260 71 31 DATA DECAY-FLAG 23260 71 32 B NO-DIM 23260 71 33 0.657 1. 23260 71 34 0.661 2. 23260 71 35 ENDDATA 4 0 23260 71 36 ENDSUBENT 35 0 23260 7199999 SUBENT 23260072 20151013 224523260 72 1 BIB 5 12 23260 72 2 REACTION (38-SR-84(N,G)38-SR-85-G,M+,SIG) 23260 72 3 (F2*SIGm)+SIGg ; F2=0.866+-0.004 ; 23260 72 4 SIG-0 - the neutron capture cross-section 23260 72 5 for neutrons at an average energy of E0=25.3 meV 23260 72 6 or velocity v0=2200 m/s. 23260 72 7 ANALYSIS Derived from directly measured data. 23260 72 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 72 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 72 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 72 11 (DEP,23260073) Directly measured data. 23260 72 12 HISTORY (20151013A) SD: SF4=Sr-85->Sr-85g, SF5=M+ (IT=87%) in 23260 72 13 REACTION code following N.Otsuka's remark. 23260 72 14 ENDBIB 12 0 23260 72 15 COMMON 1 3 23260 72 16 EN 23260 72 17 EV 23260 72 18 0.0253 23260 72 19 ENDCOMMON 3 0 23260 72 20 DATA 2 1 23260 72 21 DATA DATA-ERR 23260 72 22 B B 23260 72 23 0.700 0.007 23260 72 24 ENDDATA 3 0 23260 72 25 ENDSUBENT 24 0 23260 7299999 SUBENT 23260073 20151013 224523260 73 1 BIB 8 23 23260 73 2 REACTION (38-SR-84(N,G)38-SR-85-G,M+,SIG) 23260 73 3 Effective thermal neutron cross-section. 23260 73 4 SAMPLE - Provider - Sigma-Aldrich 23260 73 5 Matrix - SrCO(3) 23260 73 6 Elemental content, % weight - 59.351 23260 73 7 - Average sample thickness h,mm - 0.2 23260 73 8 - Average sample thickness h,mm - 0.6 23260 73 9 (38-SR-84,NAT=0.0056) 0.56+-0.01 % 23260 73 10 DECAY-DATA (38-SR-85-G,64.84D,DG,514.0,0.985) 23260 73 11 METHOD Measurements at channel Y4: 4 samples x 2 irradiation. 23260 73 12 ANALYSIS An effective thermal neutron cross-section SIG was 23260 73 13 extrapolated with aid of the k0-definition, atomic 23260 73 14 weight, isotopic composition, the gamma intensities 23260 73 15 values. 23260 73 16 Defined according to their ADS(activation decay scheme,23260 73 17 including decay branching factors). 23260 73 18 SIG-0 was derived from directly measured data. 23260 73 19 ERR-ANALYS Uncertainty is not given. 23260 73 20 Uncertainty on exp. SIG value comes from to the obs. SD23260 73 21 between all available gamma-lines. 23260 73 22 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 73 23 HISTORY (20151013A) SD: SF4=Sr-85->Sr-85g, SF5=M+ (IT=87%) in 23260 73 24 REACTION code following N.Otsuka's remark. 23260 73 25 ENDBIB 23 0 23260 73 26 COMMON 1 3 23260 73 27 EN-MEAN 23260 73 28 EV 23260 73 29 0.0253 23260 73 30 ENDCOMMON 3 0 23260 73 31 DATA 1 1 23260 73 32 DATA 23260 73 33 B 23260 73 34 0.700 23260 73 35 ENDDATA 3 0 23260 73 36 ENDSUBENT 35 0 23260 7399999 SUBENT 23260074 20141210 224123260 74 1 BIB 5 10 23260 74 2 REACTION (38-SR-86(N,G)38-SR-87-M,,SIG) 23260 74 3 SIG-0 - the neutron capture cross-section 23260 74 4 for neutrons at an average energy of E0=25.3 meV 23260 74 5 or velocity v0=2200 m/s. 23260 74 6 DECAY-DATA (38-SR-87-M,2.803HR) 23260 74 7 ANALYSIS Derived from directly measured data. 23260 74 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 74 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 74 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 74 11 (DEP,23260075) Directly measured data. 23260 74 12 ENDBIB 10 0 23260 74 13 COMMON 1 3 23260 74 14 EN 23260 74 15 EV 23260 74 16 0.0253 23260 74 17 ENDCOMMON 3 0 23260 74 18 DATA 2 1 23260 74 19 DATA DATA-ERR 23260 74 20 B B 23260 74 21 0.791 0.009 23260 74 22 ENDDATA 3 0 23260 74 23 ENDSUBENT 22 0 23260 7499999 SUBENT 23260075 20141210 224123260 75 1 BIB 7 23 23260 75 2 REACTION (38-SR-86(N,G)38-SR-87-M,,SIG) 23260 75 3 Effective thermal neutron cross-section. 23260 75 4 SAMPLE - Provider - Sigma-Aldrich 23260 75 5 Matrix - SrCO(3) 23260 75 6 Elemental content, % weight - 59.351 23260 75 7 - Average sample thickness h,mm - 0.2 23260 75 8 - Average sample thickness h,mm - 0.6 23260 75 9 (38-SR-86,NAT=0.0986) 9.86+-0.01 % 23260 75 10 DECAY-DATA (38-SR-87-M,2.803HR,DG,388.5,0.824) 23260 75 11 METHOD Measurements at channels: 23260 75 12 S84 * 2 samples x 4 irradiation ; 23260 75 13 Y4 and Cavity 4 samples x 2 irradiation. 23260 75 14 ANALYSIS An effective thermal neutron cross-section SIG was 23260 75 15 extrapolated with aid of the k0-definition, atomic 23260 75 16 weight, isotopic composition, the gamma intensities 23260 75 17 values. 23260 75 18 Defined according to their ADS(activation decay scheme,23260 75 19 including decay branching factors). 23260 75 20 SIG-0 was derived from directly measured data. 23260 75 21 ERR-ANALYS Uncertainty is not given. 23260 75 22 Uncertainty on exp. SIG value comes from to the obs. SD23260 75 23 between all available gamma-lines. 23260 75 24 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 75 25 ENDBIB 23 0 23260 75 26 COMMON 1 3 23260 75 27 EN 23260 75 28 EV 23260 75 29 0.0253 23260 75 30 ENDCOMMON 3 0 23260 75 31 DATA 1 1 23260 75 32 DATA 23260 75 33 B 23260 75 34 0.791 23260 75 35 ENDDATA 3 0 23260 75 36 ENDSUBENT 35 0 23260 7599999 SUBENT 23260076 20141210 224123260 76 1 BIB 4 9 23260 76 2 REACTION (40-ZR-96(N,G)40-ZR-97,,SIG) 23260 76 3 SIG-0 - the neutron capture cross-section 23260 76 4 for neutrons at an average energy of E0=25.3 meV 23260 76 5 or velocity v0=2200 m/s. 23260 76 6 ANALYSIS Derived from directly measured data. 23260 76 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 76 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 76 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 76 10 (DEP,23260077) Directly measured data. 23260 76 11 ENDBIB 9 0 23260 76 12 COMMON 1 3 23260 76 13 EN 23260 76 14 EV 23260 76 15 0.0253 23260 76 16 ENDCOMMON 3 0 23260 76 17 DATA 2 1 23260 76 18 DATA DATA-ERR 23260 76 19 B B 23260 76 20 0.0211 0.0002 23260 76 21 ENDDATA 3 0 23260 76 22 ENDSUBENT 21 0 23260 7699999 SUBENT 23260077 20141210 224123260 77 1 BIB 8 31 23260 77 2 REACTION (40-ZR-96(N,G)40-ZR-97,,SIG) 23260 77 3 Effective thermal neutron cross-section. 23260 77 4 SAMPLE Provider - Alfa Aesar 23260 77 5 Matrix - Foil 23260 77 6 Elemental content, % weight - 99.8 23260 77 7 Average sample thickness h,mm - 0.127 23260 77 8 (40-ZR-96,NAT=0.0280) 2.80+-0.09 % 23260 77 9 DECAY-DATA (40-ZR-97,16.74HR) 23260 77 10 ((1.)41-NB-97-M,52.7SEC,DG,743.4,0.979) at Y4 . 23260 77 11 ((2.)41-NB-97-G,72.1MIN,DG,657.9,0.982) at X26 . 23260 77 12 METHOD Measurements at channel Y4 : 4 samples x 4 irradiation,23260 77 13 X26 : 4 samples x 4 irradiation. 23260 77 14 ANALYSIS An effective thermal neutron cross-section SIG was 23260 77 15 extrapolated with aid of the k0-definition, atomic 23260 77 16 weight, isotopic composition, the gamma intensities 23260 77 17 values. 23260 77 18 Defined according to their ADS(activation decay scheme,23260 77 19 including decay branching factors). 23260 77 20 ERR-ANALYS Not given. 23260 77 21 Uncertainty on exp. SIG value comes from to the obs. SD23260 77 22 between all available gamma-lines. 23260 77 23 ADD-RES Measured k0-values with one-sigma uncertainty: 23260 77 24 E-gamma,keV k0, no-dim. 23260 77 25 753.4 1.28E-5 (+-1.7%) 23260 77 26 657.9 1.30E-5 (+-1.7%) 23260 77 27 Q0 value from literature - 251.6 (+-1.%) recommended; 23260 77 28 adopted because Q0>>f for any channel in this work. 23260 77 29 Er value from references - 338. eV (+-2%). 23260 77 30 From: Table 5 of J,JRN,302,655,2014; 23260 77 31 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260 77 32 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 77 33 ENDBIB 31 0 23260 77 34 COMMON 1 3 23260 77 35 EN-MEAN 23260 77 36 EV 23260 77 37 0.0253 23260 77 38 ENDCOMMON 3 0 23260 77 39 DATA 2 2 23260 77 40 DATA DECAY-FLAG 23260 77 41 B NO-DIM 23260 77 42 0.0211 1. 23260 77 43 0.0213 2. 23260 77 44 ENDDATA 4 0 23260 77 45 ENDSUBENT 44 0 23260 7799999 SUBENT 23260078 20141210 224123260 78 1 BIB 4 9 23260 78 2 REACTION (42-MO-100(N,G)42-MO-101,,SIG) 23260 78 3 SIG-0 - the neutron capture cross-section 23260 78 4 for neutrons at an average energy of E0=25.3 meV 23260 78 5 or velocity v0=2200 m/s. 23260 78 6 ANALYSIS Derived from directly measured data. 23260 78 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 78 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 78 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 78 10 (DEP,23260079) Directly measured data. 23260 78 11 ENDBIB 9 0 23260 78 12 COMMON 1 3 23260 78 13 EN 23260 78 14 EV 23260 78 15 0.0253 23260 78 16 ENDCOMMON 3 0 23260 78 17 DATA 2 1 23260 78 18 DATA DATA-ERR 23260 78 19 B B 23260 78 20 0.201 0.001 23260 78 21 ENDDATA 3 0 23260 78 22 ENDSUBENT 21 0 23260 7899999 SUBENT 23260079 20141210 224123260 79 1 BIB 7 27 23260 79 2 REACTION (42-MO-100(N,G)42-MO-101,,SIG) 23260 79 3 Effective thermal neutron cross-section. 23260 79 4 SAMPLE Provider - Goodfellow 23260 79 5 Matrix - Foil 23260 79 6 Elemental content, % weight - 99.9 23260 79 7 Average sample thickness h,mm - 0.025 23260 79 8 (42-MO-100,NAT=0.0982) 9.82+-0.31 % 23260 79 9 DECAY-DATA ((1.)42-MO-101,14.61MIN,DG,191.9,0.1821) 23260 79 10 ((2.)42-MO-101,14.61MIN,DG,505.1,0.1162) 23260 79 11 ((3.)42-MO-101,14.61MIN,DG,590.1,0.205) reference line 23260 79 12 ((4.)42-MO-101,14.61MIN,DG,695.6,0.665) 23260 79 13 ((5.)42-MO-101,14.61MIN,DG,1011.1,0.146) 23260 79 14 ((6.)43-TC-101,14.2MIN,DG,127.2,0.0263) 23260 79 15 ((7.)43-TC-101,14.2MIN,DG,184.1,0.0160) 23260 79 16 ((8.)43-TC-101,14.2MIN,DG,306.8,0.890)reference line 23260 79 17 ((9.)43-TC-101,14.2MIN,DG,545.1,0.0596) 23260 79 18 METHOD Measurements at channel S84 : 1 samples x 8 irradiation23260 79 19 ANALYSIS An effective thermal neutron cross-section SIG was 23260 79 20 extrapolated with aid of the k0-definition, atomic 23260 79 21 weight, isotopic composition, the gamma intensities 23260 79 22 values. 23260 79 23 Defined according to their ADS(activation decay scheme,23260 79 24 including decay branching factors). 23260 79 25 ERR-ANALYS Not given. 23260 79 26 Uncertainty on exp. SIG value comes from to the obs. SD23260 79 27 between all available gamma-lines. 23260 79 28 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 79 29 ENDBIB 27 0 23260 79 30 COMMON 1 3 23260 79 31 EN-MEAN 23260 79 32 EV 23260 79 33 0.0253 23260 79 34 ENDCOMMON 3 0 23260 79 35 DATA 2 9 23260 79 36 DATA DECAY-FLAG 23260 79 37 B NO-DIM 23260 79 38 0.201 1. 23260 79 39 0.200 2. 23260 79 40 0.200 3. 23260 79 41 0.200 4. 23260 79 42 0.201 5. 23260 79 43 0.219 6. 23260 79 44 0.201 7. 23260 79 45 0.201 8. 23260 79 46 0.201 9. 23260 79 47 ENDDATA 11 0 23260 79 48 ENDSUBENT 47 0 23260 7999999 SUBENT 23260080 20141210 224123260 80 1 BIB 4 9 23260 80 2 REACTION (44-RU-96(N,G)44-RU-97,,SIG) 23260 80 3 SIG-0 - the neutron capture cross-section 23260 80 4 for neutrons at an average energy of E0=25.3 meV 23260 80 5 or velocity v0=2200 m/s. 23260 80 6 ANALYSIS Derived from directly measured data. 23260 80 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 80 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 80 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 80 10 (DEP,23260081) Directly measured data. 23260 80 11 ENDBIB 9 0 23260 80 12 COMMON 1 3 23260 80 13 EN 23260 80 14 EV 23260 80 15 0.0253 23260 80 16 ENDCOMMON 3 0 23260 80 17 DATA 2 1 23260 80 18 DATA DATA-ERR 23260 80 19 B B 23260 80 20 0.248 0.002 23260 80 21 ENDDATA 3 0 23260 80 22 ENDSUBENT 21 0 23260 8099999 SUBENT 23260081 20141210 224123260 81 1 BIB 7 27 23260 81 2 REACTION (44-RU-96(N,G)44-RU-97,,SIG) 23260 81 3 Effective thermal neutron cross-section. 23260 81 4 SAMPLE - Provider - Alfa Aesar 23260 81 5 Matrix - Foil,Pt Alloy 23260 81 6 Elemental content, % weight - 4.6 23260 81 7 Average sample thickness h,mm - 0.05 23260 81 8 - Provider - Alfa Aesar 23260 81 9 Matrix - Liquid on paper 23260 81 10 Elemental content, % weight - 0.1 23260 81 11 Average sample thickness h,mm - 1.25 23260 81 12 (44-RU-96,NAT=0.0554) 5.54+-0.14 % 23260 81 13 DECAY-DATA ((1.)44-RU-97,2.9D,DG,215.7,0.856) reference line 23260 81 14 ((2.)44-RU-97,2.9D,DG,324.5,0.1079) 23260 81 15 METHOD Measurements at channels - 23260 81 16 Y4 : 4 samples x matrix, 23260 81 17 S84 : 4 samples x matrix, 23260 81 18 2 irradiation x channel. 23260 81 19 ANALYSIS An effective thermal neutron cross-section SIG was 23260 81 20 extrapolated with aid of the k0-definition, atomic 23260 81 21 weight, isotopic composition, the gamma intensities 23260 81 22 values. 23260 81 23 Defined according to their ADS(activation decay scheme,23260 81 24 including decay branching factors). 23260 81 25 ERR-ANALYS Not given. 23260 81 26 Uncertainty on exp. SIG value comes from to the obs. SD23260 81 27 between all available gamma-lines. 23260 81 28 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 81 29 ENDBIB 27 0 23260 81 30 COMMON 1 3 23260 81 31 EN-MEAN 23260 81 32 EV 23260 81 33 0.0253 23260 81 34 ENDCOMMON 3 0 23260 81 35 DATA 2 2 23260 81 36 DATA DECAY-FLAG 23260 81 37 B NO-DIM 23260 81 38 0.2478 1. 23260 81 39 0.2478 2. 23260 81 40 ENDDATA 4 0 23260 81 41 ENDSUBENT 40 0 23260 8199999 SUBENT 23260082 20141210 224123260 82 1 BIB 4 9 23260 82 2 REACTION (44-RU-102(N,G)44-RU-103,,SIG) 23260 82 3 SIG-0 - the neutron capture cross-section 23260 82 4 for neutrons at an average energy of E0=25.3 meV 23260 82 5 or velocity v0=2200 m/s. 23260 82 6 ANALYSIS Derived from directly measured data. 23260 82 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 82 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 82 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 82 10 (DEP,23260083) Directly measured data. 23260 82 11 ENDBIB 9 0 23260 82 12 COMMON 1 3 23260 82 13 EN 23260 82 14 EV 23260 82 15 0.0253 23260 82 16 ENDCOMMON 3 0 23260 82 17 DATA 2 1 23260 82 18 DATA DATA-ERR 23260 82 19 B B 23260 82 20 1.241 0.001 23260 82 21 ENDDATA 3 0 23260 82 22 ENDSUBENT 21 0 23260 8299999 SUBENT 23260083 20141210 224123260 83 1 BIB 7 27 23260 83 2 REACTION (44-RU-102(N,G)44-RU-103,,SIG) 23260 83 3 Effective thermal neutron cross-section. 23260 83 4 SAMPLE - Provider - Alfa Aesar 23260 83 5 Matrix - Foil,Pt Alloy 23260 83 6 Elemental content, % weight - 4.6 23260 83 7 Average sample thickness h,mm - 0.05 23260 83 8 - Provider - Alfa Aesar 23260 83 9 Matrix - Liquid on paper 23260 83 10 Elemental content, % weight - 0.1 23260 83 11 Average sample thickness h,mm - 1.25 23260 83 12 (44-RU-102,NAT=0.3155) 31.55+-0.14 % 23260 83 13 DECAY-DATA ((1.)44-RU-103,39.35D,DG,497.1,0.910) reference line 23260 83 14 ((2.)44-RU-103,39.35D,DG,610.3,0.0576) 23260 83 15 METHOD Measurements at channels - 23260 83 16 Y4 : 4 samples x matrix, 23260 83 17 S84 : 4 samples x matrix. 23260 83 18 2 irradiation x channel. 23260 83 19 ANALYSIS An effective thermal neutron cross-section SIG was 23260 83 20 extrapolated with aid of the k0-definition, atomic 23260 83 21 weight, isotopic composition, the gamma intensities 23260 83 22 values. 23260 83 23 Defined according to their ADS(activation decay scheme,23260 83 24 including decay branching factors). 23260 83 25 ERR-ANALYS Not given. 23260 83 26 Uncertainty on exp. SIG value comes from to the obs. SD23260 83 27 between all available gamma-lines. 23260 83 28 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 83 29 ENDBIB 27 0 23260 83 30 COMMON 1 3 23260 83 31 EN-MEAN 23260 83 32 EV 23260 83 33 0.0253 23260 83 34 ENDCOMMON 3 0 23260 83 35 DATA 2 2 23260 83 36 DATA DECAY-FLAG 23260 83 37 B NO-DIM 23260 83 38 1.241 1. 23260 83 39 1.242 2. 23260 83 40 ENDDATA 4 0 23260 83 41 ENDSUBENT 40 0 23260 8399999 SUBENT 23260084 20141210 224123260 84 1 BIB 4 9 23260 84 2 REACTION (44-RU-104(N,G)44-RU-105,,SIG) 23260 84 3 SIG-0 - the neutron capture cross-section 23260 84 4 for neutrons at an average energy of E0=25.3 meV 23260 84 5 or velocity v0=2200 m/s. 23260 84 6 ANALYSIS Derived from directly measured data. 23260 84 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 84 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 84 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 84 10 (DEP,23260085) Directly measured data. 23260 84 11 ENDBIB 9 0 23260 84 12 COMMON 1 3 23260 84 13 EN 23260 84 14 EV 23260 84 15 0.0253 23260 84 16 ENDCOMMON 3 0 23260 84 17 DATA 2 1 23260 84 18 DATA DATA-ERR 23260 84 19 B B 23260 84 20 0.505 0.005 23260 84 21 ENDDATA 3 0 23260 84 22 ENDSUBENT 21 0 23260 8499999 SUBENT 23260085 20181012 227323260 85 1 BIB 8 35 23260 85 2 REACTION (44-RU-104(N,G)44-RU-105,,SIG) 23260 85 3 Effective thermal neutron cross-section. 23260 85 4 SAMPLE - Provider - Alfa Aesar 23260 85 5 Matrix - Foil,Pt Alloy 23260 85 6 Elemental content, % weight - 4.6 23260 85 7 Average sample thickness h,mm - 0.05 23260 85 8 - Provider - Alfa Aesar 23260 85 9 Matrix - Liquid on paper 23260 85 10 Elemental content, % weight - 0.1 23260 85 11 Average sample thickness h,mm - 1.25 23260 85 12 (44-RU-104,NAT=0.1862) 18.62+-0.27 % 23260 85 13 DECAY-DATA ((1.)44-RU-105,4.44HR,DG,262.8,0.0657) 23260 85 14 ((2.)44-RU-105,4.44HR,DG,316.4,0.111) 23260 85 15 ((3.)44-RU-105,4.44HR,DG,469.4,0.175) 23260 85 16 ((4.)44-RU-105,4.44HR,DG,676.4,0.157) 23260 85 17 ((5.)44-RU-105,4.44HR,DG,724.3,0.473) reference line 23260 85 18 ((6.)45-RH-105-M,42.3SEC,DG,129.6,0.200) reference line23260 85 19 ((7.)45-RH-105-G,35.36HR,DG,306.1,0.051) 23260 85 20 ((8.)45-RH-105-G,35.36HR,DG,318.9,0.191) reference line23260 85 21 METHOD Measurements at channels - 23260 85 22 Y4 : 4 samples x matrix, 23260 85 23 S84 : 4 samples x matrix. 23260 85 24 2 irradiation x channel. 23260 85 25 ANALYSIS An effective thermal neutron cross-section SIG was 23260 85 26 extrapolated with aid of the k0-definition, atomic 23260 85 27 weight, isotopic composition, the gamma intensities 23260 85 28 values. 23260 85 29 Defined according to their ADS(activation decay scheme,23260 85 30 including decay branching factors). 23260 85 31 ERR-ANALYS Not given. 23260 85 32 Uncertainty on exp. SIG value comes from to the obs. SD23260 85 33 between all available gamma-lines. 23260 85 34 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 85 35 HISTORY (20181012A) SD: 134 mb -> 508 mb (typo in the article, 23260 85 36 remark from Dr F.Farina Arbocco). 23260 85 37 ENDBIB 35 0 23260 85 38 COMMON 1 3 23260 85 39 EN-MEAN 23260 85 40 EV 23260 85 41 0.0253 23260 85 42 ENDCOMMON 3 0 23260 85 43 DATA 2 8 23260 85 44 DATA DECAY-FLAG 23260 85 45 B NO-DIM 23260 85 46 0.507 1. 23260 85 47 0.508 2. 23260 85 48 0.506 3. 23260 85 49 0.505 4. 23260 85 50 0.508 5. 23260 85 51 0.508 6. 23260 85 52 0.508 7. 23260 85 53 0.499 8. 23260 85 54 ENDDATA 10 0 23260 85 55 ENDSUBENT 54 0 23260 8599999 SUBENT 23260086 20141210 224123260 86 1 BIB 4 9 23260 86 2 REACTION (46-PD-108(N,G)46-PD-109,,SIG) 23260 86 3 SIG-0 - the neutron capture cross-section 23260 86 4 for neutrons at an average energy of E0=25.3 meV 23260 86 5 or velocity v0=2200 m/s. 23260 86 6 ANALYSIS Derived from directly measured data. 23260 86 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 86 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 86 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 86 10 (DEP,23260087) Directly measured data. 23260 86 11 ENDBIB 9 0 23260 86 12 COMMON 1 3 23260 86 13 EN 23260 86 14 EV 23260 86 15 0.0253 23260 86 16 ENDCOMMON 3 0 23260 86 17 DATA 2 1 23260 86 18 DATA DATA-ERR 23260 86 19 B B 23260 86 20 8.57 0.09 23260 86 21 ENDDATA 3 0 23260 86 22 ENDSUBENT 21 0 23260 8699999 SUBENT 23260087 20141210 224123260 87 1 BIB 7 27 23260 87 2 REACTION (46-PD-108(N,G)46-PD-109,,SIG) 23260 87 3 Effective thermal neutron cross-section. 23260 87 4 SAMPLE Provider - Goodfellow 23260 87 5 Matrix - Wire 23260 87 6 Elemental content, % weight > 99.99 23260 87 7 Average sample thickness h,mm - 0.5 23260 87 8 (46-PD-108,0.2646) 26.46+-0.09 23260 87 9 DECAY-DATA ((1.)46-PD-109-G,13.46HR,DG,311.4,0.00032) 23260 87 10 ((2.)46-PD-109-G,13.46HR,DG,602.5,0.00008) 23260 87 11 ((3.)46-PD-109-G,13.46HR,DG,636.3,0.00010) 23260 87 12 ((4.)46-PD-109-G,13.46HR,DG,647.3,0.000244) 23260 87 13 reference line. 23260 87 14 ((5.)46-PD-109-G,13.46HR,DG,781.4,0.000112) 23260 87 15 ((6.)47-AG-109-M,39.6SEC,DG,88.0,0.037) reference line 23260 87 16 METHOD Measurements at channels - 23260 87 17 Y4 : 4 samples x 2 irradiations, 23260 87 18 Cavity : 2 samples x 4 irradiations. 23260 87 19 ANALYSIS An effective thermal neutron cross-section SIG was 23260 87 20 extrapolated with aid of the k0-definition, atomic 23260 87 21 weight, isotopic composition, the gamma intensities 23260 87 22 values. 23260 87 23 Defined according to their ADS(activation decay scheme,23260 87 24 including decay branching factors). 23260 87 25 ERR-ANALYS Not given. 23260 87 26 Uncertainty on exp. SIG value comes from to the obs. SD23260 87 27 between all available gamma-lines. 23260 87 28 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 87 29 ENDBIB 27 0 23260 87 30 COMMON 1 3 23260 87 31 EN-MEAN 23260 87 32 EV 23260 87 33 0.0253 23260 87 34 ENDCOMMON 3 0 23260 87 35 DATA 2 6 23260 87 36 DATA DECAY-FLAG 23260 87 37 B NO-DIM 23260 87 38 8.49 1. 23260 87 39 8.62 2. 23260 87 40 8.70 3. 23260 87 41 8.51 4. 23260 87 42 8.53 5. 23260 87 43 7.96 6. 23260 87 44 ENDDATA 8 0 23260 87 45 ENDSUBENT 44 0 23260 8799999 SUBENT 23260088 20141210 224123260 88 1 BIB 5 10 23260 88 2 REACTION (46-PD-110(N,G)46-PD-111-M,,SIG) 23260 88 3 SIG-0 - the neutron capture cross-section 23260 88 4 for neutrons at an average energy of E0=25.3 meV 23260 88 5 or velocity v0=2200 m/s. 23260 88 6 DECAY-DATA (46-PD-111-M,5.5HR) 23260 88 7 ANALYSIS Derived from directly measured data. 23260 88 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 88 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 88 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 88 11 (DEP,23260089) Directly measured data. 23260 88 12 ENDBIB 10 0 23260 88 13 COMMON 1 3 23260 88 14 EN 23260 88 15 EV 23260 88 16 0.0253 23260 88 17 ENDCOMMON 3 0 23260 88 18 DATA 2 1 23260 88 19 DATA DATA-ERR 23260 88 20 B B 23260 88 21 0.0130 0.0002 23260 88 22 ENDDATA 3 0 23260 88 23 ENDSUBENT 22 0 23260 8899999 SUBENT 23260089 20141210 224123260 89 1 BIB 7 22 23260 89 2 REACTION (46-PD-110(N,G)46-PD-111-M,,SIG) 23260 89 3 Effective thermal neutron cross-section. 23260 89 4 SAMPLE Provider - Goodfellow 23260 89 5 Matrix - Wire 23260 89 6 Elemental content, % weight > 99.99 23260 89 7 Average sample thickness h,mm - 0.5 23260 89 8 (46-PD-110,NAT=0.1172) 11.72+-0.09 % 23260 89 9 DECAY-DATA (46-PD-111-M,5.5HR,DG,172.2,0.340) reference line 23260 89 10 METHOD Measurements at channels - 23260 89 11 Y4 : 4 samples x 2 irradiations, 23260 89 12 Cavity : 2 samples x 4 irradiations. 23260 89 13 ANALYSIS An effective thermal neutron cross-section SIG was 23260 89 14 extrapolated with aid of the k0-definition, atomic 23260 89 15 weight, isotopic composition, the gamma intensities 23260 89 16 values. 23260 89 17 Defined according to their ADS(activation decay scheme,23260 89 18 including decay branching factors). 23260 89 19 ERR-ANALYS Not given. 23260 89 20 Uncertainty on exp. SIG value comes from to the obs. SD23260 89 21 between all available gamma-lines. 23260 89 22 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 89 23 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 89 24 ENDBIB 22 0 23260 89 25 COMMON 1 3 23260 89 26 EN-MEAN 23260 89 27 EV 23260 89 28 0.0253 23260 89 29 ENDCOMMON 3 0 23260 89 30 DATA 1 1 23260 89 31 DATA 23260 89 32 B 23260 89 33 0.0130 23260 89 34 ENDDATA 3 0 23260 89 35 ENDSUBENT 34 0 23260 8999999 SUBENT 23260090 20141210 224123260 90 1 BIB 4 9 23260 90 2 REACTION (46-PD-110(N,G)46-PD-111,,SIG) 23260 90 3 SIG-0 - the neutron capture cross-section 23260 90 4 for neutrons at an average energy of E0=25.3 meV 23260 90 5 or velocity v0=2200 m/s. 23260 90 6 ANALYSIS Derived from directly measured data. 23260 90 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 90 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 90 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 90 10 (DEP,23260091) Directly measured data. 23260 90 11 ENDBIB 9 0 23260 90 12 COMMON 1 3 23260 90 13 EN 23260 90 14 EV 23260 90 15 0.0253 23260 90 16 ENDCOMMON 3 0 23260 90 17 DATA 2 1 23260 90 18 DATA DATA-ERR 23260 90 19 B B 23260 90 20 0.291 0.004 23260 90 21 ENDDATA 3 0 23260 90 22 ENDSUBENT 21 0 23260 9099999 SUBENT 23260091 20141210 224123260 91 1 BIB 7 21 23260 91 2 REACTION (46-PD-110(N,G)46-PD-111,,SIG) 23260 91 3 Effective thermal neutron cross-section. 23260 91 4 SAMPLE Provider - Goodfellow 23260 91 5 Matrix - Wire 23260 91 6 Elemental content, % weight > 99.99 23260 91 7 Average sample thickness h,mm - 0.5 23260 91 8 (46-PD-110,NAT=0.1172) 11.72+-0.9 % 23260 91 9 DECAY-DATA (46-PD-111-G,23.4MIN) 23260 91 10 ((1.)47-AG-111-G,7.45D,DG,245.4,0.0124) 23260 91 11 ((2.)47-AG-111-G,7.45D,DG,342.0,0.0670) reference line 23260 91 12 METHOD Measurement at channel Y4 23260 91 13 ANALYSIS An effective thermal neutron cross-section SIG was 23260 91 14 extrapolated with aid of the k0-definition, atomic 23260 91 15 weight, isotopic composition, the gamma intensities 23260 91 16 values. 23260 91 17 Defined according to their ADS(activation decay scheme,23260 91 18 including decay branching factors). 23260 91 19 ERR-ANALYS Not given. 23260 91 20 Uncertainty on exp. SIG value comes from to the obs. SD23260 91 21 between all available gamma-lines. 23260 91 22 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 91 23 ENDBIB 21 0 23260 91 24 COMMON 1 3 23260 91 25 EN-MEAN 23260 91 26 EV 23260 91 27 0.0253 23260 91 28 ENDCOMMON 3 0 23260 91 29 DATA 2 2 23260 91 30 DATA DECAY-FLAG 23260 91 31 B NO-DIM 23260 91 32 0.2753 1. 23260 91 33 0.3075 2. 23260 91 34 ENDDATA 4 0 23260 91 35 ENDSUBENT 34 0 23260 9199999 SUBENT 23260092 20141210 224123260 92 1 BIB 4 8 23260 92 2 REACTION (46-PD-110(N,G)46-PD-111-M/G,,SIG/RAT) 23260 92 3 DECAY-DATA (46-PD-111-G,23.4MIN) 23260 92 4 (46-PD-111-M,5.5HR) 23260 92 5 ANALYSIS No explanation. 23260 92 6 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 92 7 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 92 8 (DEP,23260088) Metastable state c-s 23260 92 9 (DEP,23260090) G+M c-s 23260 92 10 ENDBIB 8 0 23260 92 11 COMMON 1 3 23260 92 12 EN 23260 92 13 EV 23260 92 14 0.0253 23260 92 15 ENDCOMMON 3 0 23260 92 16 DATA 1 1 23260 92 17 DATA 23260 92 18 NO-DIM 23260 92 19 0.0466 23260 92 20 ENDDATA 3 0 23260 92 21 ENDSUBENT 20 0 23260 9299999 SUBENT 23260093 20141210 224123260 93 1 BIB 5 10 23260 93 2 REACTION (47-AG-109(N,G)47-AG-110-M,,SIG) 23260 93 3 SIG-0 - the neutron capture cross-section 23260 93 4 for neutrons at an average energy of E0=25.3 meV 23260 93 5 or velocity v0=2200 m/s. 23260 93 6 DECAY-DATA (47-AG-110-M,249.8D) 23260 93 7 ANALYSIS Derived from directly measured data. 23260 93 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 93 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 93 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 93 11 (DEP,23260094) Directly measured data. 23260 93 12 ENDBIB 10 0 23260 93 13 COMMON 1 3 23260 93 14 EN 23260 93 15 EV 23260 93 16 0.0253 23260 93 17 ENDCOMMON 3 0 23260 93 18 DATA 2 1 23260 93 19 DATA DATA-ERR 23260 93 20 B B 23260 93 21 3.96 0.02 23260 93 22 ENDDATA 3 0 23260 93 23 ENDSUBENT 22 0 23260 9399999 SUBENT 23260094 20141210 224123260 94 1 BIB 7 35 23260 94 2 REACTION (47-AG-109(N,G)47-AG-110-M,,SIG) 23260 94 3 Effective thermal neutron cross-section. 23260 94 4 SAMPLE Provider - IRMM 23260 94 5 Matrix - Foil,Al alloy 23260 94 6 Elemental content, % weight - 1. 23260 94 7 Average sample thickness h,mm - 0.1 23260 94 8 (47-AG-109,NAT=0.48161) 48.161+-0.008 % 23260 94 9 DECAY-DATA ((1.)47-AG-110-M,249.8D,DG,446.8,0.037) 23260 94 10 ((2.)47-AG-110-M,249.8D,DG,620.4,0.0273) 23260 94 11 ((3.)47-AG-110-M,249.8D,DG,657.8,0.9561) reference line23260 94 12 ((4.)47-AG-110-M,249.8D,DG,677.6,0.107) 23260 94 13 ((5.)47-AG-110-M,249.8D,DG,687.0,0.0653) 23260 94 14 ((6.)47-AG-110-M,249.8D,DG,706.7,0.1669) 23260 94 15 ((7.)47-AG-110-M,249.8D,DG,744.3,0.0477) 23260 94 16 ((8.)47-AG-110-M,249.8D,DG,763.9,0.226) 23260 94 17 ((9.)47-AG-110-M,249.8D,DG,818.0,0.0743) 23260 94 18 ((10.)47-AG-110-M,249.8D,DG,884.7,0.750) 23260 94 19 ((11.)47-AG-110-M,249.8D,DG,937.5,0.350) 23260 94 20 ((12.)47-AG-110-M,249.8D,DG,1384.3,0.251) 23260 94 21 ((13.)47-AG-110-M,249.8D,DG,1475.8,0.0408) 23260 94 22 ((14.)47-AG-110-M,249.8D,DG,1505.0,0.1333) 23260 94 23 ((15.)47-AG-110-M,249.8D,DG,1562.3,0.0122) 23260 94 24 METHOD Measurement at channels: 23260 94 25 Y4 - 2 samples x 4 irradiations, 23260 94 26 X26 - 4 samples x 2 irradiations. 23260 94 27 ANALYSIS An effective thermal neutron cross-section SIG was 23260 94 28 extrapolated with aid of the k0-definition, atomic 23260 94 29 weight, isotopic composition, the gamma intensities 23260 94 30 values. 23260 94 31 Defined according to their ADS(activation decay scheme,23260 94 32 including decay branching factors). 23260 94 33 ERR-ANALYS Not given. 23260 94 34 Uncertainty on exp. SIG value comes from to the obs. SD23260 94 35 between all available gamma-lines. 23260 94 36 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 94 37 ENDBIB 35 0 23260 94 38 COMMON 1 3 23260 94 39 EN-MEAN 23260 94 40 EV 23260 94 41 0.0253 23260 94 42 ENDCOMMON 3 0 23260 94 43 DATA 2 15 23260 94 44 DATA DECAY-FLAG 23260 94 45 B NO-DIM 23260 94 46 3.98 1. 23260 94 47 3.98 2. 23260 94 48 3.96 3. 23260 94 49 3.93 4. 23260 94 50 3.99 5. 23260 94 51 3.98 6. 23260 94 52 3.98 7. 23260 94 53 3.96 8. 23260 94 54 3.93 9. 23260 94 55 3.93 10. 23260 94 56 3.95 11. 23260 94 57 3.94 12. 23260 94 58 3.97 13. 23260 94 59 3.97 14. 23260 94 60 3.99 15. 23260 94 61 ENDDATA 17 0 23260 94 62 ENDSUBENT 61 0 23260 9499999 SUBENT 23260095 20141210 224123260 95 1 BIB 5 10 23260 95 2 REACTION (48-CD-114(N,G)48-CD-115-G,,SIG) 23260 95 3 SIG-0 - the neutron capture cross-section 23260 95 4 for neutrons at an average energy of E0=25.3 meV 23260 95 5 or velocity v0=2200 m/s. 23260 95 6 DECAY-DATA (48-CD-115-G,53.5HR) 23260 95 7 ANALYSIS Derived from directly measured data. 23260 95 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 95 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 95 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 95 11 (DEP,23260096) Directly measured data. 23260 95 12 ENDBIB 10 0 23260 95 13 COMMON 1 3 23260 95 14 EN 23260 95 15 EV 23260 95 16 0.0253 23260 95 17 ENDCOMMON 3 0 23260 95 18 DATA 2 1 23260 95 19 DATA DATA-ERR 23260 95 20 B B 23260 95 21 0.334 0.006 23260 95 22 ENDDATA 3 0 23260 95 23 ENDSUBENT 22 0 23260 9599999 SUBENT 23260096 20141210 224123260 96 1 BIB 7 21 23260 96 2 REACTION (48-CD-114(N,G)48-CD-115-G,,SIG) 23260 96 3 Effective thermal neutron cross-section. 23260 96 4 SAMPLE Provider - NIST 23260 96 5 Matrix - Liquid on paper 23260 96 6 Elemental content, % weight - 1. 23260 96 7 Average sample thickness h,mm - 1.25 23260 96 8 (48-CD-114,NAT=0.2873) 28.73+-0.42 % 23260 96 9 DECAY-DATA ((1.)48-CD-115-G,53.5HR,DG,527.9,0.275) reference line 23260 96 10 ((2.)49-IN-115-M,4.486HR,DG,336.2,0.458) reference line23260 96 11 METHOD Measurement at each channel: 23260 96 12 - 2 samples x 2 irradiations. 23260 96 13 ANALYSIS An effective thermal neutron cross-section SIG was 23260 96 14 extrapolated with aid of the k0-definition, atomic 23260 96 15 weight, isotopic composition, the gamma intensities 23260 96 16 values. 23260 96 17 Defined according to their ADS(activation decay scheme,23260 96 18 including decay branching factors). 23260 96 19 ERR-ANALYS Not given. 23260 96 20 Uncertainty on exp. SIG value comes from to the obs. SD23260 96 21 between all available gamma-lines. 23260 96 22 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 96 23 ENDBIB 21 0 23260 96 24 COMMON 1 3 23260 96 25 EN-MEAN 23260 96 26 EV 23260 96 27 0.0253 23260 96 28 ENDCOMMON 3 0 23260 96 29 DATA 2 2 23260 96 30 DATA DECAY-FLAG 23260 96 31 B NO-DIM 23260 96 32 0.339 1. 23260 96 33 0.330 2. 23260 96 34 ENDDATA 4 0 23260 96 35 ENDSUBENT 34 0 23260 9699999 SUBENT 23260097 20141210 224123260 97 1 BIB 5 10 23260 97 2 REACTION (49-IN-113(N,G)49-IN-114-M,,SIG) M+L(43.1msec) 23260 97 3 SIG-0 - the neutron capture cross-section 23260 97 4 for neutrons at an average energy of E0=25.3 meV 23260 97 5 or velocity v0=2200 m/s. 23260 97 6 DECAY-DATA (49-IN-114-M,49.51D) 23260 97 7 ANALYSIS Derived from directly measured data. 23260 97 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 97 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 97 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 97 11 (DEP,23260098) Directly measured data. 23260 97 12 ENDBIB 10 0 23260 97 13 COMMON 1 3 23260 97 14 EN 23260 97 15 EV 23260 97 16 0.0253 23260 97 17 ENDCOMMON 3 0 23260 97 18 DATA 2 1 23260 97 19 DATA DATA-ERR 23260 97 20 B B 23260 97 21 8.1 0.3 23260 97 22 ENDDATA 3 0 23260 97 23 ENDSUBENT 22 0 23260 9799999 SUBENT 23260098 20141210 224123260 98 1 BIB 7 33 23260 98 2 REACTION (49-IN-113(N,G)49-IN-114-M,,SIG) M+L(43.1msec) 23260 98 3 Effective thermal neutron cross-section. 23260 98 4 SAMPLE Provider - IRMM 23260 98 5 Average sample thickness h,mm - 0.1 23260 98 6 -Matrix - Foil, Sn alloy 23260 98 7 Elemental content, % weight - 15.4 23260 98 8 -Matrix - Foil, Sn alloy 23260 98 9 Elemental content, % weight - 5.15 23260 98 10 -Matrix - Foil, Al alloy 23260 98 11 Elemental content, % weight - 1. 23260 98 12 -Matrix - Foil, Al alloy 23260 98 13 Elemental content, % weight - 0.017 23260 98 14 (49-IN-113,NAT=0.0429) 4.29+-0.05 % 23260 98 15 DECAY-DATA (49-IN-114-L,43.1E-3SEC) 23260 98 16 ((1.)49-IN-114-M,49.51D,DG,190.3,0.1556) 23260 98 17 reference line23260 98 18 ((2.)49-IN-114-M,49.51D,DG,558.4,0.0439) 23260 98 19 ((3.)49-IN-114-M,49.51D,DG,725.2,0.0439) reference line23260 98 20 METHOD Measurement at channels: 23260 98 21 Y4 - 4 samples x material, 4 irradiations ( only 23260 98 22 Al-alloy). 23260 98 23 X26 - 4 samples x material, 4 irradiations ( only 23260 98 24 Sn-alloy). 23260 98 25 ANALYSIS An effective thermal neutron cross-section SIG was 23260 98 26 extrapolated with aid of the k0-definition, atomic 23260 98 27 weight, isotopic composition, the gamma intensities 23260 98 28 values. 23260 98 29 Defined according to their ADS(activation decay scheme,23260 98 30 including decay branching factors). 23260 98 31 ERR-ANALYS Not given. 23260 98 32 Uncertainty on exp. SIG value comes from to the obs. SD23260 98 33 between all available gamma-lines. 23260 98 34 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 98 35 ENDBIB 33 0 23260 98 36 COMMON 1 3 23260 98 37 EN-MEAN 23260 98 38 EV 23260 98 39 0.0253 23260 98 40 ENDCOMMON 3 0 23260 98 41 DATA 2 3 23260 98 42 DATA DECAY-FLAG 23260 98 43 B NO-DIM 23260 98 44 8.4 1. 23260 98 45 7.9 2. 23260 98 46 7.9 3. 23260 98 47 ENDDATA 5 0 23260 98 48 ENDSUBENT 47 0 23260 9899999 SUBENT 23260099 20141210 224123260 99 1 BIB 5 11 23260 99 2 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG) M1+M2 23260 99 3 SIG-0 - the neutron capture cross-section 23260 99 4 for neutrons at an average energy of E0=25.3 meV 23260 99 5 or velocity v0=2200 m/s. 23260 99 6 DECAY-DATA (49-IN-116-M1,54.41MIN) 23260 99 7 (49-IN-116-M2,2.18SEC) 23260 99 8 ANALYSIS Derived from directly measured data. 23260 99 9 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260 99 10 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260 99 11 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260 99 12 (DEP,23260100) Directly measured data. 23260 99 13 ENDBIB 11 0 23260 99 14 COMMON 1 3 23260 99 15 EN 23260 99 16 EV 23260 99 17 0.0253 23260 99 18 ENDCOMMON 3 0 23260 99 19 DATA 2 1 23260 99 20 DATA DATA-ERR 23260 99 21 B B 23260 99 22 158. 2. 23260 99 23 ENDDATA 3 0 23260 99 24 ENDSUBENT 23 0 23260 9999999 SUBENT 23260100 20141210 224123260100 1 BIB 7 35 23260100 2 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,SIG) M1+M2 23260100 3 Effective thermal neutron cross-section. 23260100 4 SAMPLE Provider - IRMM 23260100 5 Average sample thickness h,mm - 0.1 23260100 6 -Matrix - Foil, Sn alloy 23260100 7 Elemental content, % weight - 15.4 23260100 8 -Matrix - Foil, Sn alloy 23260100 9 Elemental content, % weight - 5.15 23260100 10 -Matrix - Foil, Al alloy 23260100 11 Elemental content, % weight - 1. 23260100 12 -Matrix - Foil, Al alloy 23260100 13 Elemental content, % weight - 0.017 23260100 14 (49-IN-115,NAT=0.9571) 95.71+-0.05 % 23260100 15 DECAY-DATA ((1.)49-IN-116-M1,54.41MIN,DG,138.3,0.037) 23260100 16 ((2.)49-IN-116-M1,54.41MIN,DG,416.9,0.272) 23260100 17 ((3.)49-IN-116-M1,54.41MIN,DG,818.7,0.1213) 23260100 18 ((4.)49-IN-116-M1,54.41MIN,DG,1097.3,0.585) 23260100 19 ((5.)49-IN-116-M1,54.41MIN,DG,1293.5,0.848) 23260100 20 reference line 23260100 21 ((6.)49-IN-116-M1,54.41MIN,DG,1507.4,0.0992) 23260100 22 ((7.)49-IN-116-M1,54.41MIN,DG,2112.1,0.1509) 23260100 23 (49-IN-116-M2,2.18SEC) 23260100 24 METHOD Measurement at channels: 23260100 25 S84 - 4 samples of deluted Al alloy x 4 irradiations 23260100 26 Cavity - 3 samples x material ( only Sn-alloy). 23260100 27 ANALYSIS An effective thermal neutron cross-section SIG was 23260100 28 extrapolated with aid of the k0-definition, atomic 23260100 29 weight, isotopic composition, the gamma intensities 23260100 30 values. 23260100 31 Defined according to their ADS(activation decay scheme,23260100 32 including decay branching factors). 23260100 33 ERR-ANALYS Not given. 23260100 34 Uncertainty on exp. SIG value comes from to the obs. SD23260100 35 between all available gamma-lines. 23260100 36 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260100 37 ENDBIB 35 0 23260100 38 COMMON 1 3 23260100 39 EN-MEAN 23260100 40 EV 23260100 41 0.0253 23260100 42 ENDCOMMON 3 0 23260100 43 DATA 2 7 23260100 44 DATA DECAY-FLAG 23260100 45 B NO-DIM 23260100 46 159. 1. 23260100 47 160. 2. 23260100 48 160. 3. 23260100 49 157. 4. 23260100 50 157. 5. 23260100 51 156. 6. 23260100 52 158. 7. 23260100 53 ENDDATA 9 0 23260100 54 ENDSUBENT 53 0 2326010099999 SUBENT 23260101 20151013 224523260101 1 BIB 5 11 23260101 2 REACTION (50-SN-112(N,G)50-SN-113-G,M+,SIG) 23260101 3 SIG-0 - the neutron capture cross-section 23260101 4 for neutrons at an average energy of E0=25.3 meV 23260101 5 or velocity v0=2200 m/s. 23260101 6 ANALYSIS Derived from directly measured data. 23260101 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260101 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260101 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260101 10 (DEP,23260102) Directly measured data. 23260101 11 HISTORY (20151013A) SD: SF4=Sn-113->Sn-113g, SF5=M+ (IT=91%) in23260101 12 REACTION code following N.Otsuka's remark. 23260101 13 ENDBIB 11 0 23260101 14 COMMON 1 3 23260101 15 EN 23260101 16 EV 23260101 17 0.0253 23260101 18 ENDCOMMON 3 0 23260101 19 DATA 2 1 23260101 20 DATA DATA-ERR 23260101 21 B B 23260101 22 0.541 0.001 23260101 23 ENDDATA 3 0 23260101 24 ENDSUBENT 23 0 2326010199999 SUBENT 23260102 20151013 224523260102 1 BIB 8 27 23260102 2 REACTION (50-SN-112(N,G)50-SN-113-G,M+,SIG) 23260102 3 Effective thermal neutron cross-section. 23260102 4 SAMPLE Provider - IRMM 23260102 5 Average sample thickness h,mm - 0.1 23260102 6 Matrix - Foil, In alloy 23260102 7 - Elemental content, % weight - 84.6 23260102 8 - Elemental content, % weight - 94.85 23260102 9 (50-SN-112,NAT=0.0097) 0.97+-0.01 % 23260102 10 DECAY-DATA (50-SN-113-M,21.4MIN) 23260102 11 ((1.)50-SN-113-G,115.1D,DG,255.1,0.0211) 23260102 12 ((2.)49-IN-113-M,99.48MIN,DG,391.7,0.6497) 23260102 13 reference line 23260102 14 METHOD Measurement at channels: 23260102 15 Y4 - 4 samples x material, 2 irradiations, 23260102 16 X26 - 4 samples x material, 2 irradiations. 23260102 17 ANALYSIS An effective thermal neutron cross-section SIG was 23260102 18 extrapolated with aid of the k0-definition, atomic 23260102 19 weight, isotopic composition, the gamma intensities 23260102 20 values. 23260102 21 Defined according to their ADS(activation decay scheme,23260102 22 including decay branching factors). 23260102 23 ERR-ANALYS Not given. 23260102 24 Uncertainty on exp. SIG value comes from to the obs. SD23260102 25 between all available gamma-lines. 23260102 26 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260102 27 HISTORY (20151013A) SD: SF4=Sn-113->Sn-113g, SF5=M+ (IT=91%) in23260102 28 REACTION code following N.Otsuka's remark. 23260102 29 ENDBIB 27 0 23260102 30 COMMON 1 3 23260102 31 EN-MEAN 23260102 32 EV 23260102 33 0.0253 23260102 34 ENDCOMMON 3 0 23260102 35 DATA 2 2 23260102 36 DATA DECAY-FLAG 23260102 37 B NO-DIM 23260102 38 0.541 1. 23260102 39 0.540 2. 23260102 40 ENDDATA 4 0 23260102 41 ENDSUBENT 40 0 2326010299999 SUBENT 23260103 20141210 224123260103 1 BIB 5 10 23260103 2 REACTION (50-SN-116(N,G)50-SN-117-M,,SIG) 23260103 3 SIG-0 - the neutron capture cross-section 23260103 4 for neutrons at an average energy of E0=25.3 meV 23260103 5 or velocity v0=2200 m/s. 23260103 6 DECAY-DATA (50-SN-117-M,13.6D) 23260103 7 ANALYSIS Derived from directly measured data. 23260103 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260103 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260103 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260103 11 (DEP,23260104) Directly measured data. 23260103 12 ENDBIB 10 0 23260103 13 COMMON 1 3 23260103 14 EN 23260103 15 EV 23260103 16 0.0253 23260103 17 ENDCOMMON 3 0 23260103 18 DATA 2 1 23260103 19 DATA DATA-ERR 23260103 20 B B 23260103 21 0.00616 0.00002 23260103 22 ENDDATA 3 0 23260103 23 ENDSUBENT 22 0 2326010399999 SUBENT 23260104 20141210 224123260104 1 BIB 7 26 23260104 2 REACTION (50-SN-116(N,G)50-SN-117-M,,SIG) 23260104 3 Effective thermal neutron cross-section. 23260104 4 SAMPLE Provider - IRMM 23260104 5 Average sample thickness h,mm - 0.1 23260104 6 Matrix - Foil, In alloy 23260104 7 - Elemental content, % weight - 84.6 23260104 8 - Elemental content, % weight - 94.85 23260104 9 (50-SN-116,NAT=0.1454) 14.54+-0.09 % 23260104 10 DECAY-DATA ((1.)50-SN-117-M,13.6D,DG,156.0,0.02113) 23260104 11 ((2.)50-SN-117-M,13.6D,DG,158.4,0.864)reference line 23260104 12 METHOD Measurement at channels: 23260104 13 Y4 - 4 samples x material, 2 irradiations, 23260104 14 X26 - 4 samples x material, 2 irradiations. 23260104 15 Thermal-to-fast conventional neutron flux ratio: 23260104 16 Y4 - 103. 23260104 17 X26 - 126. 23260104 18 ANALYSIS An effective thermal neutron cross-section SIG was 23260104 19 extrapolated with aid of the k0-definition, atomic 23260104 20 weight, isotopic composition, the gamma intensities 23260104 21 values. 23260104 22 Defined according to their ADS(activation decay scheme,23260104 23 including decay branching factors). 23260104 24 ERR-ANALYS Not given. 23260104 25 Uncertainty on exp. SIG value comes from to the obs. SD23260104 26 between all available gamma-lines. 23260104 27 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260104 28 ENDBIB 26 0 23260104 29 COMMON 1 3 23260104 30 EN-MEAN 23260104 31 EV 23260104 32 0.0253 23260104 33 ENDCOMMON 3 0 23260104 34 DATA 2 2 23260104 35 DATA DECAY-FLAG 23260104 36 B NO-DIM 23260104 37 0.00617 1. 23260104 38 0.00615 2. 23260104 39 ENDDATA 4 0 23260104 40 ENDSUBENT 39 0 2326010499999 SUBENT 23260105 20141210 224123260105 1 BIB 5 10 23260105 2 REACTION (50-SN-124(N,G)50-SN-125-G,,SIG) 23260105 3 SIG-0 - the neutron capture cross-section 23260105 4 for neutrons at an average energy of E0=25.3 meV 23260105 5 or velocity v0=2200 m/s. 23260105 6 DECAY-DATA (50-SN-125-G,9.64D) 23260105 7 ANALYSIS Derived from directly measured data. 23260105 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260105 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260105 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260105 11 (DEP,23260106) Directly measured data. 23260105 12 ENDBIB 10 0 23260105 13 COMMON 1 3 23260105 14 EN 23260105 15 EV 23260105 16 0.0253 23260105 17 ENDCOMMON 3 0 23260105 18 DATA 2 1 23260105 19 DATA DATA-ERR 23260105 20 B B 23260105 21 0.0046 0.0001 23260105 22 ENDDATA 3 0 23260105 23 ENDSUBENT 22 0 2326010599999 SUBENT 23260106 20141210 224123260106 1 BIB 7 33 23260106 2 REACTION (50-SN-124(N,G)50-SN-125-G,,SIG) 23260106 3 Effective thermal neutron cross-section. 23260106 4 SAMPLE Provider - IRMM 23260106 5 Average sample thickness h,mm - 0.1 23260106 6 Matrix - Foil, In alloy 23260106 7 - Elemental content, % weight - 84.6 23260106 8 - Elemental content, % weight - 94.85 23260106 9 (50-SN-124,NAT=0.0579) 5.79+-0.05 % 23260106 10 DECAY-DATA ((1.)50-SN-125-G,9.64D,DG,822.4,0.043) 23260106 11 ((2.)50-SN-125-G,9.64D,DG,915.6,0.041) 23260106 12 ((3.)50-SN-125-G,9.64D,DG,1067.1,0.0100) 23260106 13 (50-SN-125-G,9.64D,DG,1089.2,0.046) c-s=0.0053 b 23260106 14 ((4.)51-SB-125,2.7586YR,DG,176.3,0.0684) 23260106 15 ((5.)51-SB-125,2.7586YR,DG,427.9,0.2960) 23260106 16 ((6.)51-SB-125,2.7586YR,DG,463.4,0.1049) 23260106 17 ((7.)51-SB-125,2.7586YR,DG,600.5,0.1764) 23260106 18 ((8.)51-SB-125,2.7586YR,DG,606.6,0.498) 23260106 19 ((9.)51-SB-125,2.7586YR,DG,635.9,0.1122) 23260106 20 (50-SN-125-M,9.52MIN,DG,331.9,0.973)reference line 23260106 21 c-s=0.1190 b 23260106 22 METHOD Measurement at channels: 23260106 23 Y4 - 4 samples x material, 2 irradiations, 23260106 24 X26 - 4 samples x material, 2 irradiations. 23260106 25 ANALYSIS An effective thermal neutron cross-section SIG was 23260106 26 extrapolated with aid of the k0-definition, atomic 23260106 27 weight, isotopic composition, the gamma intensities 23260106 28 values. 23260106 29 Defined according to their ADS(activation decay scheme,23260106 30 including decay branching factors). 23260106 31 ERR-ANALYS Not given. 23260106 32 Uncertainty on exp. SIG value comes from to the obs. SD23260106 33 between all available gamma-lines. 23260106 34 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260106 35 ENDBIB 33 0 23260106 36 COMMON 1 3 23260106 37 EN-MEAN 23260106 38 EV 23260106 39 0.0253 23260106 40 ENDCOMMON 3 0 23260106 41 DATA 2 9 23260106 42 DATA DECAY-FLAG 23260106 43 B NO-DIM 23260106 44 0.0048 1. 23260106 45 0.0045 2. 23260106 46 0.0045 3. 23260106 47 0.0045 4. 23260106 48 0.0046 5. 23260106 49 0.0046 6. 23260106 50 0.0046 7. 23260106 51 0.0046 8. 23260106 52 0.0046 9. 23260106 53 ENDDATA 11 0 23260106 54 ENDSUBENT 53 0 2326010699999 SUBENT 23260107 20141210 224123260107 1 BIB 4 9 23260107 2 REACTION (51-SB-121(N,G)51-SB-122,,SIG) 23260107 3 SIG-0 - the neutron capture cross-section 23260107 4 for neutrons at an average energy of E0=25.3 meV 23260107 5 or velocity v0=2200 m/s. 23260107 6 ANALYSIS Derived from directly measured data. 23260107 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260107 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260107 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260107 10 (DEP,23260108) Directly measured data. 23260107 11 ENDBIB 9 0 23260107 12 COMMON 1 3 23260107 13 EN 23260107 14 EV 23260107 15 0.0253 23260107 16 ENDCOMMON 3 0 23260107 17 DATA 2 1 23260107 18 DATA DATA-ERR 23260107 19 B B 23260107 20 5.766 0.008 23260107 21 ENDDATA 3 0 23260107 22 ENDSUBENT 21 0 2326010799999 SUBENT 23260108 20141210 224123260108 1 BIB 7 23 23260108 2 REACTION (51-SB-121(N,G)51-SB-122,,SIG) 23260108 3 Effective thermal neutron cross-section. 23260108 4 SAMPLE Provider - IRMM 23260108 5 Matrix - Foil, Al alloy 23260108 6 Elemental content, % weight - 1. 23260108 7 Average sample thickness h,mm - 0.1 23260108 8 (51-SB-121,NAT=0.5721) 57.21+-0.05 23260108 9 DECAY-DATA ((1.)51-SB-122-G,2.724D,DG,564.2,0.7067) reference line23260108 10 ((2.)51-SB-122-G,2.724D,DG,692.7,0.0385) 23260108 11 METHOD Measurement at channels: 23260108 12 Y4 - 2 samples x 4 irradiations, 23260108 13 S84 - 2 samples x 4 irradiations, 23260108 14 X26 - 1 sample x 2 irradiations. 23260108 15 ANALYSIS An effective thermal neutron cross-section SIG was 23260108 16 extrapolated with aid of the k0-definition, atomic 23260108 17 weight, isotopic composition, the gamma intensities 23260108 18 values. 23260108 19 Defined according to their ADS(activation decay scheme,23260108 20 including decay branching factors). 23260108 21 ERR-ANALYS Not given. 23260108 22 Uncertainty on exp. SIG value comes from to the obs. SD23260108 23 between all available gamma-lines. 23260108 24 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260108 25 ENDBIB 23 0 23260108 26 COMMON 1 3 23260108 27 EN-MEAN 23260108 28 EV 23260108 29 0.0253 23260108 30 ENDCOMMON 3 0 23260108 31 DATA 2 2 23260108 32 DATA DECAY-FLAG 23260108 33 B NO-DIM 23260108 34 5.772 1. 23260108 35 5.7615 2. 23260108 36 ENDDATA 4 0 23260108 37 ENDSUBENT 36 0 2326010899999 SUBENT 23260109 20151013 224523260109 1 BIB 5 11 23260109 2 REACTION (51-SB-123(N,G)51-SB-124-G,M+,SIG) 23260109 3 SIG-0 - the neutron capture cross-section 23260109 4 for neutrons at an average energy of E0=25.3 meV 23260109 5 or velocity v0=2200 m/s. 23260109 6 ANALYSIS Derived from directly measured data. 23260109 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260109 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260109 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260109 10 (DEP,23260110) Directly measured data. 23260109 11 HISTORY (20151013A) SD: SF4=Sb-124->Sb-124g, SF5=M+ (IT=75%) in23260109 12 REACTION code following N.Otsuka's remark. 23260109 13 ENDBIB 11 0 23260109 14 COMMON 1 3 23260109 15 EN 23260109 16 EV 23260109 17 0.0253 23260109 18 ENDCOMMON 3 0 23260109 19 DATA 2 1 23260109 20 DATA DATA-ERR 23260109 21 B B 23260109 22 3.89 0.03 23260109 23 ENDDATA 3 0 23260109 24 ENDSUBENT 23 0 2326010999999 SUBENT 23260110 20151013 224523260110 1 BIB 8 35 23260110 2 REACTION (51-SB-123(N,G)51-SB-124-G,M+,SIG) 23260110 3 Effective thermal neutron cross-section. 23260110 4 SAMPLE Provider - IRMM 23260110 5 Matrix - Foil, Al alloy 23260110 6 Elemental content, % weight - 1. 23260110 7 Average sample thickness h,mm - 0.1 23260110 8 (51-SB-123,NAT=0.4279) 42.79+-0.05 23260110 9 DECAY-DATA ((1.)51-SB-124-G,60.2D,DG,602.7,0.978) reference line 23260110 10 ((2.)51-SB-124-G,60.2D,DG,645.9,0.0742) 23260110 11 ((3.)51-SB-124-G,60.2D,DG,709.3,0.01353) 23260110 12 ((4.)51-SB-124-G,60.2D,DG,713.8,0.02276) 23260110 13 ((5.)51-SB-124-G,60.2D,DG,722.8,0.1076) 23260110 14 ((6.)51-SB-124-G,60.2D,DG,968.2,0.01882) 23260110 15 ((7.)51-SB-124-G,60.2D,DG,1045.1,0.01833) 23260110 16 ((8.)51-SB-124-G,60.2D,DG,1325.5,0.0158) 23260110 17 ((9.)51-SB-124-G,60.2D,DG,1368.2,0.02624) 23260110 18 ((10.)51-SB-124-G,60.2D,DG,1436.6,0.1217) 23260110 19 ((11.)51-SB-124-G,60.2D,DG,1691.0,0.4757) 23260110 20 ((12.)51-SB-124-G,60.2D,DG,2090.9,0.0549) 23260110 21 METHOD Measurement at channels: 23260110 22 Y4 - 2 samples x 4 irradiations, 23260110 23 S84 - 2 samples x 4 irradiations, 23260110 24 X26 - 1 sample x 2 irradiations. 23260110 25 ANALYSIS An effective thermal neutron cross-section SIG was 23260110 26 extrapolated with aid of the k0-definition, atomic 23260110 27 weight, isotopic composition, the gamma intensities 23260110 28 values. 23260110 29 Defined according to their ADS(activation decay scheme,23260110 30 including decay branching factors). 23260110 31 ERR-ANALYS Not given. 23260110 32 Uncertainty on exp. SIG value comes from to the obs. SD23260110 33 between all available gamma-lines. 23260110 34 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260110 35 HISTORY (20151013A) SD: SF4=Sb-124->Sb-124g, SF5=M+ (IT=75%) in23260110 36 REACTION code following N.Otsuka's remark. 23260110 37 ENDBIB 35 0 23260110 38 COMMON 1 3 23260110 39 EN-MEAN 23260110 40 EV 23260110 41 0.0253 23260110 42 ENDCOMMON 3 0 23260110 43 DATA 2 12 23260110 44 DATA DECAY-FLAG 23260110 45 B NO-DIM 23260110 46 3.90 1. 23260110 47 3.88 2. 23260110 48 3.90 3. 23260110 49 3.87 4. 23260110 50 3.89 5. 23260110 51 3.93 6. 23260110 52 3.88 7. 23260110 53 3.84 8. 23260110 54 3.89 9. 23260110 55 3.90 10. 23260110 56 3.94 11. 23260110 57 3.91 12. 23260110 58 ENDDATA 14 0 23260110 59 ENDSUBENT 58 0 2326011099999 SUBENT 23260111 20141210 224123260111 1 BIB 5 10 23260111 2 REACTION (56-BA-134(N,G)56-BA-135-M,,SIG) 23260111 3 SIG-0 - the neutron capture cross-section 23260111 4 for neutrons at an average energy of E0=25.3 meV 23260111 5 or velocity v0=2200 m/s. 23260111 6 DECAY-DATA (56-BA-135-M,28.7HR) 23260111 7 ANALYSIS Derived from directly measured data. 23260111 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260111 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260111 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260111 11 (DEP,23260112) Directly measured data. 23260111 12 ENDBIB 10 0 23260111 13 COMMON 1 3 23260111 14 EN 23260111 15 EV 23260111 16 0.0253 23260111 17 ENDCOMMON 3 0 23260111 18 DATA 2 1 23260111 19 DATA DATA-ERR 23260111 20 B B 23260111 21 0.054 0.001 23260111 22 ENDDATA 3 0 23260111 23 ENDSUBENT 22 0 2326011199999 SUBENT 23260112 20141210 224123260112 1 BIB 7 24 23260112 2 REACTION (56-BA-134(N,G)56-BA-135-M,,SIG) 23260112 3 Effective thermal neutron cross-section. 23260112 4 SAMPLE Provider - Sigma-Aldrich 23260112 5 Matrix - BaO 23260112 6 Elemental content, % weight - 89.565 23260112 7 Average sample thickness h,mm - 0.15 23260112 8 (56-BA-134,NAT=0.02417) 2.417+-0.018 23260112 9 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.160) 23260112 10 METHOD Measurement at channels: 23260112 11 Y4 - 2 samples x 3 irradiations, 23260112 12 S84 - 2 samples x 2 irradiations, 23260112 13 X26 - 2 sample x 2 irradiations. 23260112 14 Thermal-to-fast conventional neutron flux ratio: 23260112 15 Y4 - 103., S84 - 24., X26 - 126. 23260112 16 ANALYSIS An effective thermal neutron cross-section SIG was 23260112 17 extrapolated with aid of the k0-definition, atomic 23260112 18 weight, isotopic composition, the gamma intensities 23260112 19 values. 23260112 20 Defined according to their ADS(activation decay scheme,23260112 21 including decay branching factors). 23260112 22 ERR-ANALYS Not given. 23260112 23 Uncertainty on exp. SIG value comes from to the obs. SD23260112 24 between all available gamma-lines. 23260112 25 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260112 26 ENDBIB 24 0 23260112 27 COMMON 1 3 23260112 28 EN-MEAN 23260112 29 EV 23260112 30 0.0253 23260112 31 ENDCOMMON 3 0 23260112 32 DATA 1 1 23260112 33 DATA 23260112 34 B 23260112 35 0.054 23260112 36 ENDDATA 3 0 23260112 37 ENDSUBENT 36 0 2326011299999 SUBENT 23260113 20141210 224123260113 1 BIB 6 14 23260113 2 REACTION (63-EU-151(N,G)63-EU-152-G+M2,,SIG) 23260113 3 SIG-0 - the neutron capture cross-section 23260113 4 for neutrons at an average energy of E0=25.3 meV 23260113 5 or velocity v0=2200 m/s. 23260113 6 COMMENT Negligible contribution from 152m2Eu (96 min, IT 100%) 23260113 7 to 152gEu was considered by authors : 23260113 8 its cross-section contribution is just 4 b (0.07% of 23260113 9 the ground state value). It was not subtracted. 23260113 10 DECAY-DATA (63-EU-152-G,13.54YR) 23260113 11 ANALYSIS Derived from directly measured data. 23260113 12 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260113 13 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260113 14 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260113 15 (DEP,23260114) Directly measured data. 23260113 16 ENDBIB 14 0 23260113 17 COMMON 1 3 23260113 18 EN 23260113 19 EV 23260113 20 0.0253 23260113 21 ENDCOMMON 3 0 23260113 22 DATA 2 1 23260113 23 DATA DATA-ERR 23260113 24 B B 23260113 25 6612. 36. 23260113 26 ENDDATA 3 0 23260113 27 ENDSUBENT 26 0 2326011399999 SUBENT 23260114 20141210 224123260114 1 BIB 9 64 23260114 2 REACTION (63-EU-151(N,G)63-EU-152-G+M2,,SIG) 23260114 3 Effective thermal neutron cross-section. 23260114 4 SAMPLE Provider - Alfa Aesar 23260114 5 Matrix - Liquid on paper 23260114 6 Elemental content, % weight - 0.1 23260114 7 Average sample thickness h,mm - 1.25 23260114 8 (63-EU-151,NAT=0.4781) 47.81+-0.06 % 23260114 9 DECAY-DATA ((1.)63-EU-152-G,13.54YR,DG,121.8,0.287) 23260114 10 ((2.)63-EU-152-G,13.54YR,DG,244.7,0.0761) 23260114 11 ((3.)63-EU-152-G,13.54YR,DG,344.3,0.266) 23260114 12 ((4.)63-EU-152-G,13.54YR,DG,444.0,0.03158) 23260114 13 ((5.)63-EU-152-G,13.54YR,DG,778.9,0.1296) 23260114 14 ((6.)63-EU-152-G,13.54YR,DG,867.4,0.0426) 23260114 15 ((7.)63-EU-152-G,13.54YR,DG,963.4,0.1479) 23260114 16 ((8.)63-EU-152-G,13.54YR,DG,1084.0,0.1024) 23260114 17 ((9.)63-EU-152-G,13.54YR,DG,1112.1,0.1369) 23260114 18 ((10.)63-EU-152-G,13.54YR,DG,1408.0,0.2107) 23260114 19 reference line 23260114 20 METHOD Measurement at channels: 23260114 21 Y4 - 2 samples x 3 irradiations, 23260114 22 S84 - 2 samples x 3 irradiations, 23260114 23 X26 - 2 sample x 2 irradiations. 23260114 24 ANALYSIS An effective thermal neutron cross-section SIG was 23260114 25 extrapolated with aid of the k0-definition, atomic 23260114 26 weight, isotopic composition, the gamma intensities 23260114 27 values. 23260114 28 Defined according to their ADS(activation decay scheme,23260114 29 including decay branching factors). 23260114 30 COMMENT Negligible contribution from 152m2Eu (96 min, IT 100%) 23260114 31 to 152gEu was considered by authors : 23260114 32 its cross-section contribution is just 4 b (0.07% of 23260114 33 the ground state value). It was not subtracted. 23260114 34 ERR-ANALYS Not given. 23260114 35 Uncertainty on exp. SIG value comes from to the obs. SD23260114 36 between all available gamma-lines. 23260114 37 ADD-RES Measured k0-values with one-sigma uncertainty: 23260114 38 E-gamma,keV k0, no-dim. 23260114 39 121.8 1.23E+1 (+-5.4%) 23260114 40 244.7 3.29E+0 (+-5.1%) 23260114 41 344.3 1.15E+1 (+-5.0%) 23260114 42 444.0 1.39E+0 (+-5.1%) 23260114 43 778.9 5.68E+0 (+-5.2%) 23260114 44 867.4 1.86E+0 (+-5.1%) 23260114 45 963.4 6.42E+0 (+-5.1%) 23260114 46 1084.0 4.46E+0 (+-5.1%) 23260114 47 1112.1 5.92E+0 (+-5.0%) 23260114 48 1408.0 9.13E+0 (+-5.0%) 23260114 49 The s0 factors were determined by approaches: 23260114 50 1- the classical method: from the mean (AVG) and 23260114 51 observed SD of the results from all channels employed, 23260114 52 when inputting the recommended Er value from 23260114 53 references - 5.80 eV (+-4.%). 23260114 54 2- the a-vector method applied on up to 3 irradiation 23260114 55 channels: leading to simultaneous s0 and Er 23260114 56 determination. 23260114 57 s0 factors : 23260114 58 1- channel S84 - 0.05 (+-5%), channel Y4 - 0.04(+-3.%),23260114 59 channel X26 - 0.06 (+-4%); average - 0.05 (+-18%) ; 23260114 60 2- 0.05 (+-5.%). 23260114 61 Effective resonance energy Er defined by 23260114 62 a-vector method - 0.17 (+-20.%). 23260114 63 From: Table 5 of J,JRN,302,655,2014; 23260114 64 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260114 65 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260114 66 ENDBIB 64 0 23260114 67 COMMON 1 3 23260114 68 EN-MEAN 23260114 69 EV 23260114 70 0.0253 23260114 71 ENDCOMMON 3 0 23260114 72 DATA 2 10 23260114 73 DATA DECAY-FLAG 23260114 74 B NO-DIM 23260114 75 6589. 1. 23260114 76 6574. 2. 23260114 77 6604. 3. 23260114 78 6671. 4. 23260114 79 6669. 5. 23260114 80 6637. 6. 23260114 81 6598. 7. 23260114 82 6631. 8. 23260114 83 6583. 9. 23260114 84 6591. 10. 23260114 85 ENDDATA 12 0 23260114 86 ENDSUBENT 85 0 2326011499999 SUBENT 23260115 20141210 224123260115 1 BIB 4 9 23260115 2 REACTION (63-EU-153(N,G)63-EU-154,,SIG) 23260115 3 SIG-0 - the neutron capture cross-section 23260115 4 for neutrons at an average energy of E0=25.3 meV 23260115 5 or velocity v0=2200 m/s. 23260115 6 ANALYSIS Derived from directly measured data. 23260115 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260115 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260115 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260115 10 (DEP,23260116) Directly measured data. 23260115 11 ENDBIB 9 0 23260115 12 COMMON 1 3 23260115 13 EN 23260115 14 EV 23260115 15 0.0253 23260115 16 ENDCOMMON 3 0 23260115 17 DATA 2 1 23260115 18 DATA DATA-ERR 23260115 19 B B 23260115 20 312. 3. 23260115 21 ENDDATA 3 0 23260115 22 ENDSUBENT 21 0 2326011599999 SUBENT 23260116 20141210 224123260116 1 BIB 8 58 23260116 2 REACTION (63-EU-153(N,G)63-EU-154,,SIG) M+G 23260116 3 Effective thermal neutron cross-section. 23260116 4 SAMPLE Provider - Alfa Aesar 23260116 5 Matrix - Liquid on paper 23260116 6 Elemental content, % weight - 0.1 23260116 7 Average sample thickness h,mm - 1.25 23260116 8 (63-EU-153,NAT=0.5219) 52.19+-0.06 % 23260116 9 DECAY-DATA ((1.)63-EU-154-G,8.593YR,DG,123.1,0.404) 23260116 10 ((2.)63-EU-154-G,8.593YR,DG,248.0,0.0689) 23260116 11 ((3.)63-EU-154-G,8.593YR,DG,591.8,0.495) 23260116 12 ((4.)63-EU-154-G,8.593YR,DG,692.4,0.01777) 23260116 13 ((5.)63-EU-154-G,8.593YR,DG,723.3,0.2006) 23260116 14 ((6.)63-EU-154-G,8.593YR,DG,756.9,0.0452) 23260116 15 ((7.)63-EU-154-G,8.593YR,DG,873.2,0.1208) 23260116 16 ((8.)63-EU-154-G,8.593YR,DG,996.4,0.1048) 23260116 17 ((9.)63-EU-154-G,8.593YR,DG,1274.4,0.3480) 23260116 18 ((10.)63-EU-154-G,8.593YR,DG,1596.5,0.01797) 23260116 19 (63-EU-154-M,46.0MIN) 23260116 20 METHOD Measurement at channels: 23260116 21 Y4 - 2 samples x 3 irradiations, 23260116 22 S84 - 2 samples x 3 irradiations, 23260116 23 X26 - 2 sample x 2 irradiations. 23260116 24 ANALYSIS An effective thermal neutron cross-section SIG was 23260116 25 extrapolated with aid of the k0-definition, atomic 23260116 26 weight, isotopic composition, the gamma intensities 23260116 27 values. 23260116 28 Defined according to their ADS(activation decay scheme,23260116 29 including decay branching factors). 23260116 30 ERR-ANALYS Not given. 23260116 31 Uncertainty on exp. SIG value comes from to the obs. SD23260116 32 between all available gamma-lines. 23260116 33 ADD-RES Measured k0-values with one-sigma uncertainty: 23260116 34 E-gamma,keV k0, no-dim. 23260116 35 123.1 9.04E-1 (+-2.1%) 23260116 36 248.0 1.54E-1 (+-2.0%) 23260116 37 591.8 1.09E-1 (+-2.5%) 23260116 38 692.4 4.02E-2 (+-2.2%) 23260116 39 723.3 4.50E-1 (+-2.2%) 23260116 40 756.9 1.06E-1 (+-2.0%) 23260116 41 873.2 2.71E-1 (+-2.3%) 23260116 42 996.4 2.35E-1 (+-2.2%) 23260116 43 1274.4 7.77E-1 (+-2.2%) 23260116 44 1596.5 4.07E-2 (+-2.4%) 23260116 45 The s0 factors were determined by approaches: 23260116 46 1- the classical method: from the mean (AVG) and 23260116 47 observed SD of the results from all channels employed, 23260116 48 when inputting the recommended Er value from 23260116 49 references - 5.80 eV (+-4.%). 23260116 50 2- the a-vector method applied on up to 3 irradiation 23260116 51 channels: leading to simultaneous s0 and Er 23260116 52 determination. 23260116 53 s0 factors : 23260116 54 1- channel S84 - 4.86 (+-5%), channel Y4 - 4.71(+-3.%),23260116 55 channel X26 - 4.77 (+-4%); average - 4.75 (+-3%) ; 23260116 56 2- 4.81 (+-3.%). 23260116 57 Effective resonance energy Er defined by 23260116 58 a-vector method - 7.25 (+-20.%). 23260116 59 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260116 60 ENDBIB 58 0 23260116 61 COMMON 1 3 23260116 62 EN-MEAN 23260116 63 EV 23260116 64 0.0253 23260116 65 ENDCOMMON 3 0 23260116 66 DATA 2 10 23260116 67 DATA DECAY-FLAG 23260116 68 B NO-DIM 23260116 69 312. 1. 23260116 70 311. 2. 23260116 71 306. 3. 23260116 72 315. 4. 23260116 73 313. 5. 23260116 74 327. 6. 23260116 75 312. 7. 23260116 76 313. 8. 23260116 77 311. 9. 23260116 78 315. 10. 23260116 79 ENDDATA 12 0 23260116 80 ENDSUBENT 79 0 2326011699999 SUBENT 23260117 20141210 224123260117 1 BIB 4 9 23260117 2 REACTION (64-GD-152(N,G)64-GD-153,,SIG) 23260117 3 SIG-0 - the neutron capture cross-section 23260117 4 for neutrons at an average energy of E0=25.3 meV 23260117 5 or velocity v0=2200 m/s. 23260117 6 ANALYSIS Derived from directly measured data. 23260117 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260117 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260117 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260117 10 (DEP,23260118) Directly measured data. 23260117 11 ENDBIB 9 0 23260117 12 COMMON 1 3 23260117 13 EN 23260117 14 EV 23260117 15 0.0253 23260117 16 ENDCOMMON 3 0 23260117 17 DATA 2 1 23260117 18 DATA DATA-ERR 23260117 19 B B 23260117 20 772. 2. 23260117 21 ENDDATA 3 0 23260117 22 ENDSUBENT 21 0 2326011799999 SUBENT 23260118 20141210 224123260118 1 BIB 7 20 23260118 2 REACTION (64-GD-152(N,G)64-GD-153,,SIG) 23260118 3 Effective thermal neutron cross-section. 23260118 4 SAMPLE Provider - IRMM 23260118 5 Matrix - Disk, Al alloy 23260118 6 Elemental content, % weight - 0.03 23260118 7 Average sample thickness h,mm - 1.6 23260118 8 (64-GD-152,NAT=0.0020) 0.20+-0.01 % 23260118 9 DECAY-DATA ((1.)64-GD-153,240.4D,DG,97.4,0.2901) 23260118 10 ((2.)64-GD-153,240.4D,DG,103.2,0.211) 23260118 11 METHOD Measurement at Y4 channel - 2 samples x 2 irradiations.23260118 12 ANALYSIS An effective thermal neutron cross-section SIG was 23260118 13 extrapolated with aid of the k0-definition, atomic 23260118 14 weight, isotopic composition, the gamma intensities 23260118 15 values. 23260118 16 Defined according to their ADS(activation decay scheme,23260118 17 including decay branching factors). 23260118 18 ERR-ANALYS Not given. 23260118 19 Uncertainty on exp. SIG value comes from to the obs. SD23260118 20 between all available gamma-lines. 23260118 21 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260118 22 ENDBIB 20 0 23260118 23 COMMON 1 3 23260118 24 EN-MEAN 23260118 25 EV 23260118 26 0.0253 23260118 27 ENDCOMMON 3 0 23260118 28 DATA 2 2 23260118 29 DATA DECAY-FLAG 23260118 30 B NO-DIM 23260118 31 771. 1. 23260118 32 773. 2. 23260118 33 ENDDATA 4 0 23260118 34 ENDSUBENT 33 0 2326011899999 SUBENT 23260119 20141210 224123260119 1 BIB 4 9 23260119 2 REACTION (64-GD-158(N,G)64-GD-159,,SIG) 23260119 3 SIG-0 - the neutron capture cross-section 23260119 4 for neutrons at an average energy of E0=25.3 meV 23260119 5 or velocity v0=2200 m/s. 23260119 6 ANALYSIS Derived from directly measured data. 23260119 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260119 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260119 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260119 10 (DEP,23260120) Directly measured data. 23260119 11 ENDBIB 9 0 23260119 12 COMMON 1 3 23260119 13 EN 23260119 14 EV 23260119 15 0.0253 23260119 16 ENDCOMMON 3 0 23260119 17 DATA 2 1 23260119 18 DATA DATA-ERR 23260119 19 B B 23260119 20 2.22 0.02 23260119 21 ENDDATA 3 0 23260119 22 ENDSUBENT 21 0 2326011999999 SUBENT 23260120 20141210 224123260120 1 BIB 7 19 23260120 2 REACTION (64-GD-158(N,G)64-GD-159,,SIG) 23260120 3 Effective thermal neutron cross-section. 23260120 4 SAMPLE Provider - IRMM 23260120 5 Matrix - Disk, Al alloy 23260120 6 Elemental content, % weight - 0.03 23260120 7 Average sample thickness h,mm - 1.6 23260120 8 (64-GD-158,NAT=0.2484) 24.84+-0.07 % 23260120 9 DECAY-DATA (64-GD-159,18.56HR,DG,363.5,0.1178) reference line 23260120 10 METHOD Measurement at Y4 channel - 2 samples x 2 irradiations.23260120 11 ANALYSIS An effective thermal neutron cross-section SIG was 23260120 12 extrapolated with aid of the k0-definition, atomic 23260120 13 weight, isotopic composition, the gamma intensities 23260120 14 values. 23260120 15 Defined according to their ADS(activation decay scheme,23260120 16 including decay branching factors). 23260120 17 ERR-ANALYS Not given. 23260120 18 Uncertainty on exp. SIG value comes from to the obs. SD23260120 19 between all available gamma-lines. 23260120 20 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260120 21 ENDBIB 19 0 23260120 22 COMMON 1 3 23260120 23 EN-MEAN 23260120 24 EV 23260120 25 0.0253 23260120 26 ENDCOMMON 3 0 23260120 27 DATA 1 1 23260120 28 DATA 23260120 29 B 23260120 30 2.22 23260120 31 ENDDATA 3 0 23260120 32 ENDSUBENT 31 0 2326012099999 SUBENT 23260121 20141210 224123260121 1 BIB 4 9 23260121 2 REACTION (66-DY-164(N,G)66-DY-165,,SIG) 23260121 3 SIG-0 - the neutron capture cross-section 23260121 4 for neutrons at an average energy of E0=25.3 meV 23260121 5 or velocity v0=2200 m/s. 23260121 6 ANALYSIS Derived from directly measured data. 23260121 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260121 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260121 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260121 10 (DEP,23260122) Directly measured data. 23260121 11 ENDBIB 9 0 23260121 12 COMMON 1 3 23260121 13 EN 23260121 14 EV 23260121 15 0.0253 23260121 16 ENDCOMMON 3 0 23260121 17 DATA 2 1 23260121 18 DATA DATA-ERR 23260121 19 B B 23260121 20 2649. 25. 23260121 21 ENDDATA 3 0 23260121 22 ENDSUBENT 21 0 2326012199999 SUBENT 23260122 20141210 224123260122 1 BIB 7 27 23260122 2 REACTION (66-DY-164(N,G)66-DY-165,,SIG) 23260122 3 Effective thermal neutron cross-section. 23260122 4 SAMPLE Provider - IRMM 23260122 5 Matrix - Foil, Al alloy 23260122 6 - Elemental content, % weight - 27. 23260122 7 Average sample thickness h,mm - 0.1 23260122 8 - Elemental content, % weight - 5. 23260122 9 Average sample thickness h,mm - 0.1 23260122 10 - Elemental content, % weight - 0.127 23260122 11 Average sample thickness h,mm - 0.1 23260122 12 (66-DY-164,NAT=0.28260) 28.260+-0.054 % 23260122 13 DECAY-DATA ((1.)66-DY-165-G,2.334HR,DG,94.7,0.0380) reference line23260122 14 ((2.)66-DY-165-G,2.334HR,DG,279.8,0.0053) 23260122 15 ((3.)66-DY-165-G,2.334HR,DG,361.7,0.0090) 23260122 16 ((4.)66-DY-165-G,2.334HR,DG,633.4,0.0061) 23260122 17 ((5.)66-DY-165-G,2.334HR,DG,715.3,0.0058) 23260122 18 METHOD Each channel: 2 samples x material x 3 irradiations. 23260122 19 ANALYSIS An effective thermal neutron cross-section SIG was 23260122 20 extrapolated with aid of the k0-definition, atomic 23260122 21 weight, isotopic composition, the gamma intensities 23260122 22 values. 23260122 23 Defined according to their ADS(activation decay scheme,23260122 24 including decay branching factors). 23260122 25 ERR-ANALYS Not given. 23260122 26 Uncertainty on exp. SIG value comes from to the obs. SD23260122 27 between all available gamma-lines. 23260122 28 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260122 29 ENDBIB 27 0 23260122 30 COMMON 1 3 23260122 31 EN-MEAN 23260122 32 EV 23260122 33 0.0253 23260122 34 ENDCOMMON 3 0 23260122 35 DATA 2 55 23260122 36 DATA DECAY-FLAG 23260122 37 B NO-DIM 23260122 38 2621. 1. 23260122 39 2645. 2. 23260122 40 2635. 3. 23260122 41 2600. 4. 23260122 42 2584. 5. 23260122 43 ENDDATA 7 0 23260122 44 ENDSUBENT 43 0 2326012299999 SUBENT 23260123 20141210 224123260123 1 BIB 4 9 23260123 2 REACTION (69-TM-169(N,G)69-TM-170,,SIG) 23260123 3 SIG-0 - the neutron capture cross-section 23260123 4 for neutrons at an average energy of E0=25.3 meV 23260123 5 or velocity v0=2200 m/s. 23260123 6 ANALYSIS Derived from directly measured data. 23260123 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260123 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260123 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260123 10 (DEP,23260124) Directly measured data. 23260123 11 ENDBIB 9 0 23260123 12 COMMON 1 3 23260123 13 EN 23260123 14 EV 23260123 15 0.0253 23260123 16 ENDCOMMON 3 0 23260123 17 DATA 2 1 23260123 18 DATA DATA-ERR 23260123 19 B B 23260123 20 107. 8. 23260123 21 ENDDATA 3 0 23260123 22 ENDSUBENT 21 0 2326012399999 SUBENT 23260124 20141210 224123260124 1 BIB 7 19 23260124 2 REACTION (69-TM-169(N,G)69-TM-170,,SIG) 23260124 3 Effective thermal neutron cross-section. 23260124 4 SAMPLE Provider - Alfa Aesar 23260124 5 Matrix - Liquid on paper 23260124 6 Elemental content, % weight - 0.1 23260124 7 Average sample thickness h,mm - 1.25 23260124 8 (69-TM-169,NAT=1.00) 100% 23260124 9 DECAY-DATA (69-TM-170,128.6D,DG,84.3,0.0248) 23260124 10 METHOD Measurement at Y4 channel - 2 samples x 2 irradiations.23260124 11 ANALYSIS An effective thermal neutron cross-section SIG was 23260124 12 extrapolated with aid of the k0-definition, atomic 23260124 13 weight, isotopic composition, the gamma intensities 23260124 14 values. 23260124 15 Defined according to their ADS(activation decay scheme,23260124 16 including decay branching factors). 23260124 17 ERR-ANALYS Not given. 23260124 18 Uncertainty on exp. SIG value comes from to the obs. SD23260124 19 between all available gamma-lines. 23260124 20 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260124 21 ENDBIB 19 0 23260124 22 COMMON 1 3 23260124 23 EN-MEAN 23260124 24 EV 23260124 25 0.0253 23260124 26 ENDCOMMON 3 0 23260124 27 DATA 1 15 23260124 28 DATA 23260124 29 B 23260124 30 107. 23260124 31 ENDDATA 3 0 23260124 32 ENDSUBENT 31 0 2326012499999 SUBENT 23260125 20141210 224123260125 1 BIB 4 9 23260125 2 REACTION (70-YB-168(N,G)70-YB-169,,SIG) 23260125 3 SIG-0 - the neutron capture cross-section 23260125 4 for neutrons at an average energy of E0=25.3 meV 23260125 5 or velocity v0=2200 m/s. 23260125 6 ANALYSIS Derived from directly measured data. 23260125 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260125 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260125 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260125 10 (DEP,23260126) Directly measured data. 23260125 11 ENDBIB 9 0 23260125 12 COMMON 1 3 23260125 13 EN 23260125 14 EV 23260125 15 0.0253 23260125 16 ENDCOMMON 3 0 23260125 17 DATA 2 1 23260125 18 DATA DATA-ERR 23260125 19 B B 23260125 20 3144. 34. 23260125 21 ENDDATA 3 0 23260125 22 ENDSUBENT 21 0 2326012599999 SUBENT 23260126 20141210 224123260126 1 BIB 8 50 23260126 2 REACTION (70-YB-168(N,G)70-YB-169,,SIG) M+G 23260126 3 Effective thermal neutron cross-section. 23260126 4 SAMPLE Provider - Alfa Aesar 23260126 5 Matrix - Liquid on paper 23260126 6 Elemental content, % weight - 0.1 23260126 7 Average sample thickness h,mm - 1.25 23260126 8 (70-YB-168,NAT=0.00123) 0.123+-0.003 % 23260126 9 DECAY-DATA ((1.)70-YB-169-G,32.03D,DG,93.6,0.0257) 23260126 10 ((2.)70-YB-169-G,32.03D,DG,109.8,0.1736) 23260126 11 ((3.)70-YB-169-G,32.03D,DG,130.5,0.1138) 23260126 12 ((4.)70-YB-169-G,32.03D,DG,177.2,0.2232) 23260126 13 ((5.)70-YB-169-G,32.03D,DG,198.0,0.3593) 23260126 14 ((6.)70-YB-169-G,32.03D,DG,307.7,0.10046) 23260126 15 (70-YB-169-M,46.SEC) 23260126 16 METHOD Each channel: 4 samples x 2 irradiations. 23260126 17 ANALYSIS An effective thermal neutron cross-section SIG was 23260126 18 extrapolated with aid of the k0-definition, atomic 23260126 19 weight, isotopic composition, the gamma intensities 23260126 20 values. 23260126 21 Defined according to their ADS(activation decay scheme,23260126 22 including decay branching factors). 23260126 23 ERR-ANALYS Not given. 23260126 24 Uncertainty on exp. SIG value comes from to the obs. SD23260126 25 between all available gamma-lines. 23260126 26 ADD-RES Measured k0-values with one-sigma uncertainty: 23260126 27 E-gamma,keV k0, no-dim. 23260126 28 93.6 1.20E-3 (+-5.2%) 23260126 29 109.8 8.26E-3 (+-5.1%) 23260126 30 130.5 5.28E-3 (+-5.0%) 23260126 31 177.2 1.04E-2 (+-5.4%) 23260126 32 198.0 1.68E-2 (+-5.4%) 23260126 33 307.7 4.63E-3 (+-5.4%) 23260126 34 The s0 factors were determined by approaches: 23260126 35 1- the classical method: from the mean (AVG) and 23260126 36 observed SD of the results from all channels employed, 23260126 37 when inputting the recommended Er value from 23260126 38 references - 0.61 eV . 23260126 39 2- the a-vector method applied on up to 3 irradiation 23260126 40 channels: leading to simultaneous Q0 (or s0) and Er 23260126 41 determination. 23260126 42 1- s0 factor: 23260126 43 channel S84 - 3.47 (+-3.%), channel Y4 - 4.11 (+-2.%), 23260126 44 channel X26 - 5.08 (+-5.%); average 4.17 (+-12.%); 23260126 45 2- 3.39 (+-8.%). 23260126 46 Effective resonance energy Er defined by 23260126 47 a-vector method - 0.026 (+-25.%) . 23260126 48 From:Table 5 of J,JRN,302,655,2014; 23260126 49 Suppl.material 10967-2014-3281-MOESM3-ESM.pdf 23260126 50 Table 6 of J,JRN,302,631,2014. 23260126 51 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260126 52 ENDBIB 50 0 23260126 53 COMMON 1 3 23260126 54 EN-MEAN 23260126 55 EV 23260126 56 0.0253 23260126 57 ENDCOMMON 3 0 23260126 58 DATA 2 65 23260126 59 DATA DECAY-FLAG 23260126 60 B NO-DIM 23260126 61 3151. 1. 23260126 62 3203. 2. 23260126 63 3121. 3. 23260126 64 3141. 4. 23260126 65 3148. 5. 23260126 66 3101. 6. 23260126 67 ENDDATA 8 0 23260126 68 ENDSUBENT 67 0 2326012699999 SUBENT 23260127 20141210 224123260127 1 BIB 4 9 23260127 2 REACTION (70-YB-174(N,G)70-YB-175,,SIG) 23260127 3 SIG-0 - the neutron capture cross-section 23260127 4 for neutrons at an average energy of E0=25.3 meV 23260127 5 or velocity v0=2200 m/s. 23260127 6 ANALYSIS Derived from directly measured data. 23260127 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260127 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260127 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260127 10 (DEP,23260128) Directly measured data. 23260127 11 ENDBIB 9 0 23260127 12 COMMON 1 3 23260127 13 EN 23260127 14 EV 23260127 15 0.0253 23260127 16 ENDCOMMON 3 0 23260127 17 DATA 2 1 23260127 18 DATA DATA-ERR 23260127 19 B B 23260127 20 63.0 0.5 23260127 21 ENDDATA 3 0 23260127 22 ENDSUBENT 21 0 2326012799999 SUBENT 23260128 20141210 224123260128 1 BIB 7 23 23260128 2 REACTION (70-YB-174(N,G)70-YB-175,,SIG) 23260128 3 Effective thermal neutron cross-section. 23260128 4 SAMPLE Provider - Alfa Aesar 23260128 5 Matrix - Liquid on paper 23260128 6 Elemental content, % weight - 0.1 23260128 7 Average sample thickness h,mm - 1.25 23260128 8 (70-YB-174,NAT=0.32026) 32.026+-0.080 % 23260128 9 DECAY-DATA ((1.)70-YB-175,4.185D,DG,113.8,0.0387) 23260128 10 ((2.)70-YB-175,4.185D,DG,137.7,0.00235) 23260128 11 ((3.)70-YB-175,4.185D,DG,144.9,0.00672) 23260128 12 ((4.)70-YB-175,4.185D,DG,282.5,0.0613) 23260128 13 ((5.)70-YB-175,4.185D,DG,396.3,0.132) reference line 23260128 14 METHOD Each channel: 4 samples x 2 irradiations. 23260128 15 ANALYSIS An effective thermal neutron cross-section SIG was 23260128 16 extrapolated with aid of the k0-definition, atomic 23260128 17 weight, isotopic composition, the gamma intensities 23260128 18 values. 23260128 19 Defined according to their ADS(activation decay scheme,23260128 20 including decay branching factors). 23260128 21 ERR-ANALYS Not given. 23260128 22 Uncertainty on exp. SIG value comes from to the obs. SD23260128 23 between all available gamma-lines. 23260128 24 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260128 25 ENDBIB 23 0 23260128 26 COMMON 1 3 23260128 27 EN-MEAN 23260128 28 EV 23260128 29 0.0253 23260128 30 ENDCOMMON 3 0 23260128 31 DATA 2 55 23260128 32 DATA DECAY-FLAG 23260128 33 B NO-DIM 23260128 34 63.3 1. 23260128 35 63.2 2. 23260128 36 62.9 3. 23260128 37 63.4 4. 23260128 38 62.2 5. 23260128 39 ENDDATA 7 0 23260128 40 ENDSUBENT 39 0 2326012899999 SUBENT 23260129 20141210 224123260129 1 BIB 4 9 23260129 2 REACTION (70-YB-176(N,G)70-YB-177,,SIG) 23260129 3 SIG-0 - the neutron capture cross-section 23260129 4 for neutrons at an average energy of E0=25.3 meV 23260129 5 or velocity v0=2200 m/s. 23260129 6 ANALYSIS Derived from directly measured data. 23260129 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260129 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260129 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260129 10 (DEP,23260130) Directly measured data. 23260129 11 ENDBIB 9 0 23260129 12 COMMON 1 3 23260129 13 EN 23260129 14 EV 23260129 15 0.0253 23260129 16 ENDCOMMON 3 0 23260129 17 DATA 2 1 23260129 18 DATA DATA-ERR 23260129 19 B B 23260129 20 2.85 0.07 23260129 21 ENDDATA 3 0 23260129 22 ENDSUBENT 21 0 2326012999999 SUBENT 23260130 20141210 224123260130 1 BIB 7 22 23260130 2 REACTION (70-YB-176(N,G)70-YB-177,,SIG) 23260130 3 Effective thermal neutron cross-section. 23260130 4 SAMPLE Provider - Alfa Aesar 23260130 5 Matrix - Liquid on paper 23260130 6 Elemental content, % weight - 0.1 23260130 7 Average sample thickness h,mm - 1.25 23260130 8 (70-YB-174,NAT=0.32026) 32.026+-0.080 % 23260130 9 DECAY-DATA ((1.)70-YB-177-G,1.911HR,DG,150.3,0.205) reference line23260130 10 ((2.)70-YB-177-G,1.911HR,DG,941.8,0.0108) 23260130 11 ((3.)70-YB-177-G,1.911HR,DG,1080.2,0.059) 23260130 12 ((4.)70-YB-177-G,1.911HR,DG,1241.2,0.0350) 23260130 13 METHOD Each channel: 2 samples x 8 irradiations. 23260130 14 ANALYSIS An effective thermal neutron cross-section SIG was 23260130 15 extrapolated with aid of the k0-definition, atomic 23260130 16 weight, isotopic composition, the gamma intensities 23260130 17 values. 23260130 18 Defined according to their ADS(activation decay scheme,23260130 19 including decay branching factors). 23260130 20 ERR-ANALYS Not given. 23260130 21 Uncertainty on exp. SIG value comes from to the obs. SD23260130 22 between all available gamma-lines. 23260130 23 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260130 24 ENDBIB 22 0 23260130 25 COMMON 1 3 23260130 26 EN-MEAN 23260130 27 EV 23260130 28 0.0253 23260130 29 ENDCOMMON 3 0 23260130 30 DATA 2 45 23260130 31 DATA DECAY-FLAG 23260130 32 B NO-DIM 23260130 33 2.80 1. 23260130 34 2.89 2. 23260130 35 2.85 3. 23260130 36 2.90 4. 23260130 37 ENDDATA 6 0 23260130 38 ENDSUBENT 37 0 2326013099999 SUBENT 23260131 20141210 224123260131 1 BIB 4 9 23260131 2 REACTION (72-HF-174(N,G)72-HF-175,,SIG) 23260131 3 SIG-0 - the neutron capture cross-section 23260131 4 for neutrons at an average energy of E0=25.3 meV 23260131 5 or velocity v0=2200 m/s. 23260131 6 ANALYSIS Derived from directly measured data. 23260131 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260131 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260131 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260131 10 (DEP,23260132) Directly measured data. 23260131 11 ENDBIB 9 0 23260131 12 COMMON 1 3 23260131 13 EN 23260131 14 EV 23260131 15 0.0253 23260131 16 ENDCOMMON 3 0 23260131 17 DATA 2 1 23260131 18 DATA DATA-ERR 23260131 19 B B 23260131 20 549. 6. 23260131 21 ENDDATA 3 0 23260131 22 ENDSUBENT 21 0 2326013199999 SUBENT 23260132 20141210 224123260132 1 BIB 7 20 23260132 2 REACTION (72-HF-174(N,G)72-HF-175,,SIG) 23260132 3 Effective thermal neutron cross-section. 23260132 4 SAMPLE Provider - IRMM 23260132 5 Matrix - Wire,Al alloy 23260132 6 Average sample thickness h,mm - 1. 23260132 7 -Elemental content, % weight - 5. 23260132 8 -Elemental content, % weight - 0.1 23260132 9 (72-HF-174,NAT=0.0016) 0.16+-0.01 % 23260132 10 DECAY-DATA (72-HF-175,70.D,DG,343.4,0.870) 23260132 11 METHOD Each channel: 2 samples x material x 2 irradiations. 23260132 12 ANALYSIS An effective thermal neutron cross-section SIG was 23260132 13 extrapolated with aid of the k0-definition, atomic 23260132 14 weight, isotopic composition, the gamma intensities 23260132 15 values. 23260132 16 Defined according to their ADS(activation decay scheme,23260132 17 including decay branching factors). 23260132 18 ERR-ANALYS Not given. 23260132 19 Uncertainty on exp. SIG value comes from to the obs. SD23260132 20 between all available gamma-lines. 23260132 21 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260132 22 ENDBIB 20 0 23260132 23 COMMON 1 3 23260132 24 EN-MEAN 23260132 25 EV 23260132 26 0.0253 23260132 27 ENDCOMMON 3 0 23260132 28 DATA 1 15 23260132 29 DATA 23260132 30 B 23260132 31 549. 23260132 32 ENDDATA 3 0 23260132 33 ENDSUBENT 32 0 2326013299999 SUBENT 23260133 20141210 224123260133 1 BIB 5 10 23260133 2 REACTION (72-HF-179(N,G)72-HF-180-M,,SIG) 23260133 3 SIG-0 - the neutron capture cross-section 23260133 4 for neutrons at an average energy of E0=25.3 meV 23260133 5 or velocity v0=2200 m/s. 23260133 6 DECAY-DATA (72-HF-180-M,5.5HR) 23260133 7 ANALYSIS Derived from directly measured data. 23260133 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260133 9 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260133 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260133 11 (DEP,23260134) Directly measured data. 23260133 12 ENDBIB 10 0 23260133 13 COMMON 1 3 23260133 14 EN 23260133 15 EV 23260133 16 0.0253 23260133 17 ENDCOMMON 3 0 23260133 18 DATA 2 1 23260133 19 DATA DATA-ERR 23260133 20 B B 23260133 21 0.430 0.005 23260133 22 ENDDATA 3 0 23260133 23 ENDSUBENT 22 0 2326013399999 SUBENT 23260134 20141210 224123260134 1 BIB 7 24 23260134 2 REACTION (72-HF-179(N,G)72-HF-180-M,,SIG) 23260134 3 Effective thermal neutron cross-section. 23260134 4 SAMPLE Provider - IRMM 23260134 5 Matrix - Wire,Al alloy 23260134 6 Average sample thickness h,mm - 1. 23260134 7 -Elemental content, % weight - 5. 23260134 8 -Elemental content, % weight - 0.1 23260134 9 (72-HF-179,NAT=0.1362) 23260134 10 DECAY-DATA ((1.)72-HF-180-M,5.5HR,DG,93.3,0.171) 23260134 11 ((2.)72-HF-180-M,5.5HR,DG,215.4,0.813) 23260134 12 ((3.)72-HF-180-M,5.5HR,DG,332.3,0.941) reference line 23260134 13 ((4.)72-HF-180-M,5.5HR,DG,443.2,0.819) 23260134 14 ((5.)72-HF-180-M,5.5HR,DG,500.7,0.143) 23260134 15 METHOD S84 channel: 2 samples x material x 4 irradiations. 23260134 16 ANALYSIS An effective thermal neutron cross-section SIG was 23260134 17 extrapolated with aid of the k0-definition, atomic 23260134 18 weight, isotopic composition, the gamma intensities 23260134 19 values. 23260134 20 Defined according to their ADS(activation decay scheme,23260134 21 including decay branching factors). 23260134 22 ERR-ANALYS Not given. 23260134 23 Uncertainty on exp. SIG value comes from to the obs. SD23260134 24 between all available gamma-lines. 23260134 25 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260134 26 ENDBIB 24 0 23260134 27 COMMON 1 3 23260134 28 EN-MEAN 23260134 29 EV 23260134 30 0.0253 23260134 31 ENDCOMMON 3 0 23260134 32 DATA 2 55 23260134 33 DATA DECAY-FLAG 23260134 34 B NO-DIM 23260134 35 0.437 1. 23260134 36 0.433 2. 23260134 37 0.428 3. 23260134 38 0.430 4. 23260134 39 0.424 5. 23260134 40 ENDDATA 7 0 23260134 41 ENDSUBENT 40 0 2326013499999 SUBENT 23260135 20230212 231423260135 1 BIB 6 11 23260135 2 REACTION (72-HF-180(N,G)72-HF-181,,SIG) 23260135 3 SIG-0 - the neutron capture cross-section 23260135 4 for neutrons at an average energy of E0=25.3 meV 23260135 5 or velocity v0=2200 m/s. 23260135 6 DECAY-DATA (72-HF-181,42.39D) 23260135 7 ANALYSIS Derived from directly measured data. 23260135 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260135 9 STATUS (TABLE) Table 6 of J.Radioanal.Nucl.chem.,302,655,2014;23260135 10 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260135 11 (DEP,23260136) Directly measured data. 23260135 12 HISTORY (20230212A) SD: SF4=Hf-181g -> Hf-181 in REACTION code.23260135 13 ENDBIB 11 0 23260135 14 COMMON 1 3 23260135 15 EN 23260135 16 EV 23260135 17 0.0253 23260135 18 ENDCOMMON 3 0 23260135 19 DATA 2 1 23260135 20 DATA DATA-ERR 23260135 21 B B 23260135 22 13.01 0.07 23260135 23 ENDDATA 3 0 23260135 24 ENDSUBENT 23 0 2326013599999 SUBENT 23260136 20230212 231423260136 1 BIB 8 23 23260136 2 REACTION (72-HF-180(N,G)72-HF-181,,SIG) 23260136 3 Effective thermal neutron cross-section. 23260136 4 SAMPLE Provider - IRMM 23260136 5 Matrix - Wire,Al alloy 23260136 6 Average sample thickness h,mm - 1. 23260136 7 -Elemental content, % weight - 5. 23260136 8 -Elemental content, % weight - 0.1 23260136 9 (72-HF-180,NAT=0.3508) 35.08+-0.26 % 23260136 10 DECAY-DATA ((1.)72-HF-181,42.39D,DG,133.0,0.433) 23260136 11 ((2.)72-HF-181,42.39D,DG,345.9,0.1512) 23260136 12 ((3.)72-HF-181,42.39D,DG,482.2,0.805) 23260136 13 METHOD S84 channel: 2 samples x material x 4 irradiations. 23260136 14 ANALYSIS An effective thermal neutron cross-section SIG was 23260136 15 extrapolated with aid of the k0-definition, atomic 23260136 16 weight, isotopic composition, the gamma intensities 23260136 17 values. 23260136 18 Defined according to their ADS(activation decay scheme,23260136 19 including decay branching factors). 23260136 20 ERR-ANALYS Not given. 23260136 21 Uncertainty on exp. SIG value comes from to the obs. SD23260136 22 between all available gamma-lines. 23260136 23 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260136 24 HISTORY (20230212A) SD: SF4=Hf-181g -> Hf-181 in REACTION code.23260136 25 ENDBIB 23 0 23260136 26 COMMON 1 3 23260136 27 EN-MEAN 23260136 28 EV 23260136 29 0.0253 23260136 30 ENDCOMMON 3 0 23260136 31 DATA 2 35 23260136 32 DATA DECAY-FLAG 23260136 33 B NO-DIM 23260136 34 13.08 1. 23260136 35 12.93 2. 23260136 36 13.03 3. 23260136 37 ENDDATA 5 0 23260136 38 ENDSUBENT 37 0 2326013699999 SUBENT 23260137 20141210 224123260137 1 BIB 4 9 23260137 2 REACTION (73-TA-181(N,G)73-TA-182,,SIG) 23260137 3 SIG-0 - the neutron capture cross-section 23260137 4 for neutrons at an average energy of E0=25.3 meV 23260137 5 or velocity v0=2200 m/s. 23260137 6 ANALYSIS Derived from directly measured data. 23260137 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260137 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260137 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260137 10 (DEP,23260138) Directly measured data. 23260137 11 ENDBIB 9 0 23260137 12 COMMON 1 3 23260137 13 EN 23260137 14 EV 23260137 15 0.0253 23260137 16 ENDCOMMON 3 0 23260137 17 DATA 2 1 23260137 18 DATA DATA-ERR 23260137 19 B B 23260137 20 20.2 0.1 23260137 21 ENDDATA 3 0 23260137 22 ENDSUBENT 21 0 2326013799999 SUBENT 23260138 20141210 224123260138 1 BIB 7 46 23260138 2 REACTION (73-TA-181(N,G)73-TA-182,,SIG) M+G 23260138 3 Effective thermal neutron cross-section. 23260138 4 SAMPLE - Provider - IRMM 23260138 5 Matrix - Foil 23260138 6 Elemental content, % weight > 99.99 23260138 7 Average sample thickness h,mm - 1. 23260138 8 - Provider - IRMM 23260138 9 Matrix - Foil, Y alloy 23260138 10 Elemental content, % weight - 0.7 23260138 11 Average sample thickness h,mm - 0.1 23260138 12 - Provider - NIST 23260138 13 Matrix - Liquid on paper 23260138 14 Elemental content, % weight - 1. 23260138 15 Average sample thickness h,mm - 1.25 23260138 16 (73-TA-181,NAT=0.9998799) 99.98799+-0.00032 % 23260138 17 DECAY-DATA ((1.)73-TA-182-G,114.4D,DG,84.7,0.0265) 23260138 18 ((2.)73-TA-182-G,114.4D,DG,100.1,0.142) 23260138 19 ((3.)73-TA-182-G,114.4D,DG,113.7,0.0187) 23260138 20 ((4.)73-TA-182-G,114.4D,DG,152.4,0.0702) 23260138 21 ((5.)73-TA-182-G,114.4D,DG,156.4,0.0267) 23260138 22 ((6.)73-TA-182-G,114.4D,DG,179.4,0.0312) 23260138 23 ((7.)73-TA-182-G,114.4D,DG,198.4,0.0147) 23260138 24 ((8.)73-TA-182-G,114.4D,DG,222.1,0.0757) 23260138 25 ((9.)73-TA-182-G,114.4D,DG,229.3,0.0364) 23260138 26 ((10.)73-TA-182-G,114.4D,DG,264.1,0.0361) 23260138 27 ((11.)73-TA-182-G,114.4D,DG,1001.7,0.0209) 23260138 28 ((12.)73-TA-182-G,114.4D,DG,1121.3,0.3524) 23260138 29 reference line. 23260138 30 ((13.)73-TA-182-G,114.4D,DG,1189.1,0.1649) 23260138 31 ((14.)73-TA-182-G,114.4D,DG,1221.4,0.2723) 23260138 32 ((15.)73-TA-182-G,114.4D,DG,1231.0,0.1162) 23260138 33 ((16.)73-TA-182-G,114.4D,DG,1257.4,0.0151) 23260138 34 ((17.)73-TA-182-G,114.4D,DG,1289.2,0.0137) 23260138 35 (73-TA-182-G,114.4D,DG,1157.5) 23260138 36 (73-TA-182-M2,15.8MIN) 23260138 37 METHOD Each channel: 4 samples x material x 4 irradiations. 23260138 38 ANALYSIS An effective thermal neutron cross-section SIG was 23260138 39 extrapolated with aid of the k0-definition, atomic 23260138 40 weight, isotopic composition, the gamma intensities 23260138 41 values. 23260138 42 Defined according to their ADS(activation decay scheme,23260138 43 including decay branching factors). 23260138 44 ERR-ANALYS Not given. 23260138 45 Uncertainty on exp. SIG value comes from to the obs. SD23260138 46 between all available gamma-lines. 23260138 47 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260138 48 ENDBIB 46 0 23260138 49 COMMON 1 3 23260138 50 EN-MEAN 23260138 51 EV 23260138 52 0.0253 23260138 53 ENDCOMMON 3 0 23260138 54 DATA 2 175 23260138 55 DATA DECAY-FLAG 23260138 56 B NO-DIM 23260138 57 20.3 1. 23260138 58 19.9 2. 23260138 59 20.3 3. 23260138 60 20.2 4. 23260138 61 20.3 5. 23260138 62 20.2 6. 23260138 63 20.1 7. 23260138 64 20.3 8. 23260138 65 20.4 9. 23260138 66 20.2 10. 23260138 67 20.0 11. 23260138 68 20.3 12. 23260138 69 20.1 13. 23260138 70 20.3 14. 23260138 71 20.2 15. 23260138 72 20.2 16. 23260138 73 20.2 17. 23260138 74 ENDDATA 19 0 23260138 75 ENDSUBENT 74 0 2326013899999 SUBENT 23260139 20141210 224123260139 1 BIB 5 13 23260139 2 REACTION 1(78-PT-196(N,G)78-PT-197-M,,SIG) 23260139 3 2(78-PT-196(N,G)78-PT-197-G,,SIG) 23260139 4 3(78-PT-196(N,G)78-PT-197,,SIG) 23260139 5 SIG-0 - the neutron capture cross-section 23260139 6 for neutrons at an average energy of E0=25.3 meV 23260139 7 or velocity v0=2200 m/s. 23260139 8 DECAY-DATA (78-PT-197-M,95.41MIN) 23260139 9 (78-PT-197-G,19.892HR) 23260139 10 ANALYSIS Derived from directly measured data. 23260139 11 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260139 12 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260139 13 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260139 14 (DEP,23260140) Directly measured data. 23260139 15 ENDBIB 13 0 23260139 16 COMMON 1 3 23260139 17 EN 23260139 18 EV 23260139 19 0.0253 23260139 20 ENDCOMMON 3 0 23260139 21 DATA 6 1 23260139 22 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 323260139 23 B B B B B B 23260139 24 0.0352 0.0004 0.718 0.003 0.753 0.015 23260139 25 ENDDATA 3 0 23260139 26 ENDSUBENT 25 0 2326013999999 SUBENT 23260140 20141210 224123260140 1 BIB 7 31 23260140 2 REACTION (78-PT-196(N,G)78-PT-197,,SIG) 23260140 3 Effective thermal neutron cross-section. 23260140 4 SAMPLE - Provider - Goodfellow 23260140 5 Matrix - Wire 23260140 6 Elemental content, % weight > 99.99 23260140 7 Average sample thickness h,mm - 0.5 23260140 8 - Provider - Alfa Aesar 23260140 9 Matrix - Foil,Ru alloy 23260140 10 Elemental content, % weight - 95.35 23260140 11 Average sample thickness h,mm - 0.05 23260140 12 - Provider - Alfa Aesar 23260140 13 Matrix - Liquid on paper 23260140 14 Elemental content, % weight - 0.1 23260140 15 Average sample thickness h,mm - 1.25 23260140 16 (78-PT-196,NAT=0.2521) 25.21+-0.34 % 23260140 17 DECAY-DATA (78-PT-197-M,95.41MIN,DG,346.5,0.1110) 23260140 18 reference line, c-s=0.0352 b 23260140 19 ((1.)78-PT-197-G,19.892HR,DG,191.4,0.0370) 23260140 20 reference line 23260140 21 ((2.)78-PT-197-G,19.892HR,DG,268.8,0.0023) 23260140 22 METHOD Each channel: 2 samples x material x 2 irradiations. 23260140 23 ANALYSIS An effective thermal neutron cross-section SIG was 23260140 24 extrapolated with aid of the k0-definition, atomic 23260140 25 weight, isotopic composition, the gamma intensities 23260140 26 values. 23260140 27 Defined according to their ADS(activation decay scheme,23260140 28 including decay branching factors). 23260140 29 ERR-ANALYS Not given. 23260140 30 Uncertainty on exp. SIG value comes from to the obs. SD23260140 31 between all available gamma-lines. 23260140 32 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260140 33 ENDBIB 31 0 23260140 34 COMMON 1 3 23260140 35 EN-MEAN 23260140 36 EV 23260140 37 0.0253 23260140 38 ENDCOMMON 3 0 23260140 39 DATA 2 25 23260140 40 DATA DECAY-FLAG 23260140 41 B NO-DIM 23260140 42 0.752 1. 23260140 43 0.751 2. 23260140 44 ENDDATA 4 0 23260140 45 ENDSUBENT 44 0 2326014099999 SUBENT 23260141 20141210 224123260141 1 BIB 4 9 23260141 2 REACTION (78-PT-198(N,G)78-PT-199,,SIG) 23260141 3 SIG-0 - the neutron capture cross-section 23260141 4 for neutrons at an average energy of E0=25.3 meV 23260141 5 or velocity v0=2200 m/s. 23260141 6 ANALYSIS Derived from directly measured data. 23260141 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260141 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260141 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260141 10 (DEP,23260142) Directly measured data. 23260141 11 ENDBIB 9 0 23260141 12 COMMON 1 3 23260141 13 EN 23260141 14 EV 23260141 15 0.0253 23260141 16 ENDCOMMON 3 0 23260141 17 DATA 2 1 23260141 18 DATA DATA-ERR 23260141 19 B B 23260141 20 3.30 0.01 23260141 21 ENDDATA 3 0 23260141 22 ENDSUBENT 21 0 2326014199999 SUBENT 23260142 20181012 227323260142 1 BIB 8 36 23260142 2 REACTION (78-PT-198(N,G)78-PT-199,,SIG) 23260142 3 Effective thermal neutron cross-section. 23260142 4 SAMPLE - Provider - Goodfellow 23260142 5 Matrix - Wire 23260142 6 Elemental content, % weight > 99.99 23260142 7 Average sample thickness h,mm - 0.5 23260142 8 - Provider - Alfa Aesar 23260142 9 Matrix - Foil,Ru alloy 23260142 10 Elemental content, % weight - 95.35 23260142 11 Average sample thickness h,mm - 0.05 23260142 12 - Provider - Alfa Aesar 23260142 13 Matrix - Liquid on paper 23260142 14 Elemental content, % weight - 0.1 23260142 15 Average sample thickness h,mm - 1.25 23260142 16 (78-PT-198,NAT=0.07356) 7.356+-0.130 % 23260142 17 DECAY-DATA (78-PT-199-G,30.8MIN,DG,493.8,0.0447) c-s=3.25 b 23260142 18 (78-PT-199-G,30.8MIN,DG,543.0,0.1174) 23260142 19 reference line, c-s=3.25 b 23260142 20 (78-PT-199-G,30.8MIN,DG,714.6,0.0145) c-s=3.26 b 23260142 21 ((1.)79-AU-199,3.139D,DG,158.4,0.400) 23260142 22 ((2.)79-AU-199,3.139D,DG,208.2,0.0872) 23260142 23 (78-PT-199-M,13.6SEC,DG,391.9,0.8494) 23260142 24 reference line, c-s=0.35 b 23260142 25 METHOD Each channel: 2 samples x material x 2 irradiations. 23260142 26 ANALYSIS An effective thermal neutron cross-section SIG was 23260142 27 extrapolated with aid of the k0-definition, atomic 23260142 28 weight, isotopic composition, the gamma intensities 23260142 29 values. 23260142 30 Defined according to their ADS(activation decay scheme,23260142 31 including decay branching factors). 23260142 32 ERR-ANALYS Not given. 23260142 33 Uncertainty on exp. SIG value comes from to the obs. SD23260142 34 between all available gamma-lines. 23260142 35 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260142 36 HISTORY (20181012A) SD: Data were corrected according to 23260142 37 presentation in the table. 23260142 38 ENDBIB 36 0 23260142 39 COMMON 1 3 23260142 40 EN-MEAN 23260142 41 EV 23260142 42 0.0253 23260142 43 ENDCOMMON 3 0 23260142 44 DATA 2 25 23260142 45 DATA DECAY-FLAG 23260142 46 B NO-DIM 23260142 47 3.30 1. 23260142 48 3.29 2. 23260142 49 ENDDATA 4 0 23260142 50 ENDSUBENT 49 0 2326014299999 SUBENT 23260143 20141210 224123260143 1 BIB 4 9 23260143 2 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 23260143 3 SIG-0 - the neutron capture cross-section 23260143 4 for neutrons at an average energy of E0=25.3 meV 23260143 5 or velocity v0=2200 m/s. 23260143 6 ANALYSIS Derived from directly measured data. 23260143 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23260143 8 STATUS (TABLE) Table 6 of J,JRN,302,655,2014; 23260143 9 Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260143 10 (DEP,23260144) Directly measured data. 23260143 11 ENDBIB 9 0 23260143 12 COMMON 1 3 23260143 13 EN 23260143 14 EV 23260143 15 0.0253 23260143 16 ENDCOMMON 3 0 23260143 17 DATA 2 1 23260143 18 DATA DATA-ERR 23260143 19 B B 23260143 20 7.408 0.021 23260143 21 ENDDATA 3 0 23260143 22 ENDSUBENT 21 0 2326014399999 SUBENT 23260144 20141210 224123260144 1 BIB 7 25 23260144 2 REACTION (90-TH-232(N,G)90-TH-233,,SIG) 23260144 3 Effective thermal neutron cross-section. 23260144 4 SAMPLE - Provider - IRMM 23260144 5 Matrix - Wire, Al alloy 23260144 6 Elemental content, % weight - 0.819 23260144 7 Average sample thickness h,mm - 1. 23260144 8 (90-TH-232,NAT=1.00) 100.% 23260144 9 DECAY-DATA (90-TH-233,22.3MIN) 23260144 10 ((1.)91-PA-233,26.97D,DG,300.1,0.0663) 23260144 11 ((2.)91-PA-233,26.97D,DG,311.9,0.385) reference line 23260144 12 ((3.)91-PA-233,26.97D,DG,340.5,0.0445) 23260144 13 ((4.)91-PA-233,26.97D,DG,375.4,0.00679) 23260144 14 ((5.)91-PA-233,26.97D,DG,398.5,0.01391) 23260144 15 ((6.)91-PA-233,26.97D,DG,415.8,0.0173) 23260144 16 METHOD Each channel: 4 samples x 4 irradiations. 23260144 17 ANALYSIS An effective thermal neutron cross-section SIG was 23260144 18 extrapolated with aid of the k0-definition, atomic 23260144 19 weight, isotopic composition, the gamma intensities 23260144 20 values. 23260144 21 Defined according to their ADS(activation decay scheme,23260144 22 including decay branching factors). 23260144 23 ERR-ANALYS Not given. 23260144 24 Uncertainty on exp. SIG value comes from to the obs. SD23260144 25 between all available gamma-lines. 23260144 26 STATUS (TABLE) Suppl.material 10967-2014-3281-MOESM2-ESM.pdf 23260144 27 ENDBIB 25 0 23260144 28 COMMON 1 3 23260144 29 EN-MEAN 23260144 30 EV 23260144 31 0.0253 23260144 32 ENDCOMMON 3 0 23260144 33 DATA 2 65 23260144 34 DATA DECAY-FLAG 23260144 35 B NO-DIM 23260144 36 7.409 1. 23260144 37 7.400 2. 23260144 38 7.435 3. 23260144 39 7.371 4. 23260144 40 7.420 5. 23260144 41 7.411 6. 23260144 42 ENDDATA 8 0 23260144 43 ENDSUBENT 42 0 2326014499999 ENDENTRY 144 0 2326099999999