ENTRY 23266 20230215 231423266 0 1 SUBENT 23266001 20230215 231423266 1 1 BIB 16 110 23266 1 2 TITLE Experimental determination of k0, Q0, factors and 23266 1 3 neutron cross-sections for 41 isotopes of interest in 23266 1 4 Neutron Activation Analysis. 23266 1 5 AUTHOR (F.Farina Arbocco,P.Vermaercke,K.Smits,L.Sneyers, 23266 1 6 K.Strijckmans) 23266 1 7 REFERENCE (J,JRN,296,931,2013) 23266 1 8 #doi:10.1007/s10967-012-2132-0 23266 1 9 Also Suppl.materials: 23266 1 10 10967-2012-2132-MOESM1-ESM.pdf 23266 1 11 Figs. of exp.parameter Ya 23266 1 12 10967-2012-2132-MOESM2-ESM.pdf Table -Q0, ef.res.energy23266 1 13 10967-2012-2132-MOESM3-ESM.pdf Table -SIG, k0 23266 1 14 INSTITUTE (2BLGMOL) F.Farina Arbocco,P.Vermaercke,K.Smits, 23266 1 15 L.Sneyers. 23266 1 16 (2BLGGHT) F.Farina Arbocco,K.Strijckmans. 23266 1 17 REL-REF (M,,F.De Corte+,J,AND,85,47,2003) 23266 1 18 Activation decay schemes (ADS). k0 method. 23266 1 19 Summary of previous k0 measurements up to Dec.2002. 23266 1 20 FACILITY (REAC,2BLGMOL) Irradiation channels S84, Y4, X26 and 23266 1 21 Cavity at the BR1 reactor at SCK-CEN, Belgium. 23266 1 22 INC-SOURCE (REAC) 23266 1 23 INC-SPECT Parameters of the neutron spectra: 23266 1 24 Channel f a 23266 1 25 Y4 38.2+-0.5 0.066+-0.003 23266 1 26 S84 16.4+-0.4 -0.003+-0.005 23266 1 27 X26 95.+-5. 0.11+-0.01 23266 1 28 Cavity 70000. (pure thermal) 23266 1 29 f - ratio of the thermal neutron flux to epithermal 23266 1 30 flux, 23266 1 31 a - slope parameter of the epithermal spectrum 23266 1 32 (~1/(E**(1+a)) 23266 1 33 SAMPLE Standards were positioned within a 2 cm distance to the23266 1 34 nearest comparator along the axis of a cylindrical 23266 1 35 polyethylene container (PE rabbit) following a sandwich23266 1 36 pattern. Up to 10 samples per rabbit were irradiated on23266 1 37 each opportunity. 23266 1 38 Replicate samples were positioned inside 1 mm thick 23266 1 39 Cd covers and were irradiated on the same irradiation 23266 1 40 positions. 23266 1 41 Samples providers : 23266 1 42 - IRMM - Institute for Reference Materials and 23266 1 43 Measurements, 23266 1 44 - CBNM - Central Bureau for Nuclear Measurements, 23266 1 45 - NIST - National Institute of Standards and 23266 1 46 Technology, 23266 1 47 - Fluka, Alfa Aesar, Googfellow, Dr.Hult, 23266 1 48 Sigma-Aldrich. 23266 1 49 Au-197 samples ( ultimate comparator): 23266 1 50 - Provider - IRMM 23266 1 51 Matrix - Foil, Al alloy 23266 1 52 Weight,% - 0.1 23266 1 53 Average thickness,mm - 0.1 23266 1 54 METHOD (ACTIV) The rabbits were irradiated in channels 23266 1 55 S84, Y4, X26 and the thermal Cavity at the BR1. 23266 1 56 Channel Y4 S84 X26 Cavity 23266 1 57 Channel radius 50.mm 40.mm 40.mm 40.mm 23266 1 58 Channel length 500.mm 300.mm 300.mm 300.mm 23266 1 59 Container radius 11.1mm 10.mm 20.mm 15.mm 23266 1 60 Rabbits length 71.mm 53.mm 80.mm 60.mm 23266 1 61 Typical irr.time 7 hr 1 or 7hr 3 or 7hr 2 or 4hr 23266 1 62 ASSUMED (ASSUM,(79-AU-197(N,G)79-AU-198,,RI)/ 23266 1 63 (79-AU-197(N,G)79-AU-198,,SIG)) 23266 1 64 - Au-197 data: =5.7 eV (+-14.2.% 2 sigma), 23266 1 65 Q0=15.7 (+-3.6% 2 sigma) ; k0=1.00 23266 1 66 FCd=0.991, HL=2.695d , Gamma Energy 411.8 keV, 23266 1 67 Intensity 95.54% , SIG-0=98.65(9) b . 23266 1 68 DETECTOR (HPGE) HPGe detectors equipped with LFC modules for 23266 1 69 dead time, pulse pile-up correction. 23266 1 70 CORRECTION Epithermal and thermal self-shielding corrections 23266 1 71 factors Gt and Ge were obtained through the MATSSF and 23266 1 72 the SIGMOID calculation methods, are given in Table 1 23266 1 73 of J.Radioanal.Nucl.Chem.,296,931,2013. 23266 1 74 ERR-ANALYS Maximum expected uncertainty on an induced gamma 23266 1 75 specific activity (A) and a Cd ratio (RCd) at 1s 23266 1 76 confidence level. RCd uncertainty corresponds to the 23266 1 77 quadratic summation of twice the uncertainty reported. 23266 1 78 Contributing to Asp Uncertainty (1s),% from : 23266 1 79 Reference efficiency 0.5 23266 1 80 Efficiency transfer 0.8 23266 1 81 COI corrections 0.6 23266 1 82 Sample positioning 0.1 23266 1 83 Weighting 0.1 23266 1 84 Certified elemental content 0.5 23266 1 85 Mass losses for spiked standard 0.5 23266 1 86 Moisture content of compound 0.1 23266 1 87 Pulse pile-ups 0.3 23266 1 88 Timing 0.1 23266 1 89 Half-life 0.2 23266 1 90 Counting statistics 0.3 23266 1 91 % Total uncertainty (1s) 1.4 23266 1 92 Contributing to RCd Uncertainty (1s),% from : 23266 1 93 Sample positioning 0.1 23266 1 94 Weighting 0.1 23266 1 95 Mass losses for spiked standard 0.5 23266 1 96 Pulse pile-ups 0.3 23266 1 97 Timing 0.1 23266 1 98 Half-life 0.2 23266 1 99 Counting statistics 0.3 23266 1 100 % Total uncertainty (1s) 0.7 23266 1 101 COMMENT Of compiler. 23266 1 102 - EN-MIN-NM was taken as Cd cut-off energy 0.55 eV for23266 1 103 1 mm Cd-covers ( as mentioned in the article, page 932,23266 1 104 J,JRN,296,931,2013 ). 23266 1 105 Two sigma uncertainties DATA-ERR and ERR-SYS were 23266 1 106 converted into one sigma uncertainty ( divided by 2.) 23266 1 107 by compiler. 23266 1 108 HISTORY (20141210C) M.M. 23266 1 109 (20180202A) M.M. Misprints were corrected in Subents 23266 1 110 004,006,011,053,054,068,101,110,116,133 . 23266 1 111 (20230215A) SD: Corrections in all Subents. 23266 1 112 ENDBIB 110 0 23266 1 113 COMMON 2 3 23266 1 114 ASSUM ASSUM-ERR 23266 1 115 NO-DIM PER-CENT 23266 1 116 15.7 3.6 23266 1 117 ENDCOMMON 3 0 23266 1 118 ENDSUBENT 117 0 23266 199999 SUBENT 23266002 20230215 231423266 2 1 BIB 9 30 23266 2 2 REACTION 1((11-NA-23(N,G)11-NA-24,,RI,,AV)// 23266 2 3 (11-NA-23(N,G)11-NA-24,,SIG,,AV)) 23266 2 4 2((11-NA-23(N,G)11-NA-24,,RI)// 23266 2 5 (11-NA-23(N,G)11-NA-24,,SIG)) 23266 2 6 Q0 value (ratio of resonance integral to thermal 23266 2 7 neutron activation cross-section) 23266 2 8 SAMPLE - Provider - Fluka 23266 2 9 Matrix - High purity NaCl 23266 2 10 Elemental content, % weight - 39.320 23266 2 11 Average sample thickness, mm - 0.15 23266 2 12 - Provider - Alfa Aesar 23266 2 13 Matrix - Liquid on paper 23266 2 14 Elemental content, % weight - 0.1 23266 2 15 (11-NA-23,NAT=1.00) 23266 2 16 METHOD Measurement at channels S84, Y4,X26. 23266 2 17 DECAY-DATA (11-NA-24,14.96HR,DG,1368.6,0.99994, 23266 2 18 DG,2754.0,0.99855) 23266 2 19 ANALYSIS The Q0 factor was determined by 23266 2 20 1- the classical method: through the weighted mean and 23266 2 21 observed standard deviation of the 3 irradiation 23266 2 22 channels employed (S84, Y4, X26), when inputting 23266 2 23 factors from the literature. 23266 2 24 2- the a-vector method: through the parameters 23266 2 25 (m, b) --> determination of the value as well. 23266 2 26 ADD-RES Effective resonance Energy was defined by a-vector23266 2 27 method to be 36.74 eV ( +-8%, 2sigma). 23266 2 28 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 2 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 2 30 1(DEP,23266003) Directly measured data. 23266 2 31 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 2 32 ENDBIB 30 0 23266 2 33 COMMON 2 3 23266 2 34 EN-MIN-NM EN-DN 23266 2 35 EV EV 23266 2 36 0.55 0.0253 23266 2 37 ENDCOMMON 3 0 23266 2 38 DATA 4 1 23266 2 39 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 2 40 NO-DIM PER-CENT NO-DIM PER-CENT 23266 2 41 0.63 7.5 0.59 2. 23266 2 42 ENDDATA 3 0 23266 2 43 ENDSUBENT 42 0 23266 299999 SUBENT 23266003 20141210 224123266 3 1 BIB 7 33 23266 3 2 REACTION ((11-NA-23(N,G)11-NA-24,,RI)// 23266 3 3 (11-NA-23(N,G)11-NA-24,,SIG)) 23266 3 4 Q0 value (ratio of resonance integral to thermal 23266 3 5 neutron activation cross-section) 23266 3 6 SAMPLE - Provider - Fluka 23266 3 7 Matrix - High purity NaCl 23266 3 8 Elemental content, % weight - 39.320 23266 3 9 Average sample thickness, mm - 0.15 23266 3 10 - Provider - Alfa Aesar 23266 3 11 Matrix - Liquid on paper 23266 3 12 Elemental content, % weight - 0.1 23266 3 13 (11-NA-23,NAT=1.00) 23266 3 14 FLAG Measurement at channels: 23266 3 15 (1.) S84, 23266 3 16 (2.) Y4, 23266 3 17 (3.) X26 . 23266 3 18 DECAY-DATA (11-NA-24,14.96HR,DG,1368.6,0.99994, 23266 3 19 DG,2754.0,0.99855) 23266 3 20 ANALYSIS The Q0 factor was determined by the classical method 23266 3 21 when inputting effective resonance energy factors23266 3 22 from the literature. 23266 3 23 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 3 24 uncertainties ( 1 sigma) from: 23266 3 25 (ERR-1) alpha factor, 23266 3 26 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 3 27 epithermal flux for gold, 23266 3 28 (ERR-3) effective resonance energy , 23266 3 29 (ERR-4) Cd transmission factor FCd 23266 3 30 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 3 31 bare and Cd-covered sample. 23266 3 32 (ERR-S) Standard deviation. 23266 3 33 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 3 34 (COREL,23266002) Average data . 23266 3 35 ENDBIB 33 0 23266 3 36 COMMON 2 3 23266 3 37 EN-MIN-NM EN-DN 23266 3 38 EV EV 23266 3 39 0.55 0.0253 23266 3 40 ENDCOMMON 3 0 23266 3 41 DATA 9 3 23266 3 42 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 3 43 ERR-5 ERR-SYS FLAG 23266 3 44 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 3 45 PER-CENT PER-CENT NO-DIM 23266 3 46 0.59 1.2 1.05 0.9 0.05 0.7 23266 3 47 0.85 1.75 1. 23266 3 48 0.62 0.9 0.7 0.6 0.45 0.6 23266 3 49 0.7 1.4 2. 23266 3 50 0.72 4.85 1.4 1.05 0.7 0.55 23266 3 51 0.65 2.05 3. 23266 3 52 ENDDATA 10 0 23266 3 53 ENDSUBENT 52 0 23266 399999 SUBENT 23266004 20230215 231423266 4 1 BIB 5 12 23266 4 2 REACTION (11-NA-23(N,G)11-NA-24,,SIG,,AV) 23266 4 3 SIG-0 - the average thermal neutron cross-section 23266 4 4 for neutrons at an average energy of E0=25.3 meV 23266 4 5 or velocity v0=2200 m/s. 23266 4 6 ANALYSIS Derived from directly measured data. 23266 4 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 4 8 Uncertainty on exp. SIG-0 value comes from to the 23266 4 9 observed standard deviation between gamma-lines. 23266 4 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 4 11 (DEP,23266005) Directly measured data. 23266 4 12 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 4 13 (20230215A) SD: SF8=AV added to REACTION codes. 23266 4 14 ENDBIB 12 0 23266 4 15 COMMON 1 3 23266 4 16 EN 23266 4 17 EV 23266 4 18 0.0253 23266 4 19 ENDCOMMON 3 0 23266 4 20 DATA 2 1 23266 4 21 DATA DATA-ERR 23266 4 22 B B 23266 4 23 0.519 0.001 23266 4 24 ENDDATA 3 0 23266 4 25 ENDSUBENT 24 0 23266 499999 SUBENT 23266005 20141210 224123266 5 1 BIB 8 29 23266 5 2 REACTION (11-NA-23(N,G)11-NA-24,,SIG) 23266 5 3 Directly measured thermal neutron cross-section SIG-0 23266 5 4 SAMPLE - Provider - Fluka 23266 5 5 Matrix - High purity NaCl 23266 5 6 Elemental content, % weight - 39.320 23266 5 7 Average sample thickness, mm - 0.15 23266 5 8 - Provider - Alfa Aesar 23266 5 9 Matrix - Liquid on paper 23266 5 10 Elemental content, % weight - 0.1 23266 5 11 (11-NA-23,NAT=1.00) 23266 5 12 DECAY-DATA ((1.)11-NA-24,14.96HR,DG,1368.6,0.99994) 23266 5 13 reference line 23266 5 14 ((2.)11-NA-24,14.96HR,DG,2754.0,0.99855) 23266 5 15 METHOD Measurement at channels Y4/Cavity, S84 . 23266 5 16 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 5 17 extrapolated with aid of the k0-definition, atomic 23266 5 18 weight, isotopic composition, the gamma intensities 23266 5 19 values. 23266 5 20 Defined according to their ADS(activation decay scheme,23266 5 21 including decay branching factors). 23266 5 22 ADD-RES Measured k0-values with one-sigma uncertainty 23266 5 23 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 5 24 1368.6 4.71E-2 (+-1.9%) 23266 5 25 2754.0 4.72E-2 (+-1.6%) 23266 5 26 Effective resonance energy defined by a-vector 23266 5 27 method 36.74(8) eV. 23266 5 28 ERR-ANALYS Uncertainty is not given. 23266 5 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 5 30 (COREL,23266004) Average data 23266 5 31 ENDBIB 29 0 23266 5 32 COMMON 1 3 23266 5 33 EN 23266 5 34 EV 23266 5 35 0.0253 23266 5 36 ENDCOMMON 3 0 23266 5 37 DATA 2 2 23266 5 38 DATA DECAY-FLAG 23266 5 39 B NO-DIM 23266 5 40 0.518 1. 23266 5 41 0.520 2. 23266 5 42 ENDDATA 4 0 23266 5 43 ENDSUBENT 42 0 23266 599999 SUBENT 23266006 20230215 231423266 6 1 BIB 8 20 23266 6 2 REACTION ((12-MG-26(N,G)12-MG-27,,RI,,AV)// 23266 6 3 (12-MG-26(N,G)12-MG-27,,SIG,,AV)) 23266 6 4 Q0 value (ratio of resonance integral to thermal 23266 6 5 neutron activation cross-section) 23266 6 6 SAMPLE - Provider - Goodfellow 23266 6 7 Matrix - Foil 23266 6 8 Elemental content, % weight - >99.99 23266 6 9 Average sample thickness, mm - 0.1 23266 6 10 (12-MG-26,NAT=0.1101) 11.01+-0.03 % 23266 6 11 DECAY-DATA (12-MG-27,9.462MIN,DG,170.7,0.0086, 23266 6 12 DG,843.8,0.7180, 23266 6 13 DG,1014.4,0.2820) 23266 6 14 METHOD Measurement at channel S84 23266 6 15 ANALYSIS The Q0 factor was determined by 23266 6 16 - the classical method. 23266 6 17 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 6 18 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 6 19 (DEP,23266007) Directly measured data . 23266 6 20 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 6 21 (20230215A) SD: SF8=AV added to REACTION codes. 23266 6 22 ENDBIB 20 0 23266 6 23 COMMON 2 3 23266 6 24 EN-MIN-NM EN-DN 23266 6 25 EV EV 23266 6 26 0.55 0.0253 23266 6 27 ENDCOMMON 3 0 23266 6 28 DATA 2 1 23266 6 29 DATA DATA-ERR 23266 6 30 NO-DIM PER-CENT 23266 6 31 0.46 1.5 23266 6 32 ENDDATA 3 0 23266 6 33 ENDSUBENT 32 0 23266 699999 SUBENT 23266007 20141210 224123266 7 1 BIB 7 27 23266 7 2 REACTION ((12-MG-26(N,G)12-MG-27,,RI)// 23266 7 3 (12-MG-26(N,G)12-MG-27,,SIG)) 23266 7 4 Q0 value (ratio of resonance integral to thermal 23266 7 5 neutron activation cross-section) 23266 7 6 SAMPLE - Provider - Goodfellow 23266 7 7 Matrix - Foil 23266 7 8 Elemental content, % weight - >99.99 23266 7 9 Average sample thickness, mm - 0.1 23266 7 10 (12-MG-26,NAT=0.1101) 11.01+-0.03 % 23266 7 11 METHOD Measurement at channel S84 23266 7 12 DECAY-DATA (12-MG-27,9.462MIN,DG,170.7,0.0086,DG,843.8,0.7180, 23266 7 13 DG,1014.4,0.2820) 23266 7 14 ANALYSIS The Q0 factor was determined by the classical method 23266 7 15 when inputting effective resonance energy factors 23266 7 16 from the literature. 23266 7 17 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 7 18 uncertainties ( 1 sigma) from: 23266 7 19 (ERR-1) alpha factor, 23266 7 20 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 7 21 epithermal flux for gold, 23266 7 22 (ERR-3) effective resonance energy Er, 23266 7 23 (ERR-4) Cd transmission factor FCd 23266 7 24 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 7 25 bare and Cd-covered sample. 23266 7 26 (ERR-S) Standard deviation. 23266 7 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 7 28 (COREL,23266006) Average data . 23266 7 29 ENDBIB 27 0 23266 7 30 COMMON 2 3 23266 7 31 EN-MIN-NM EN-DN 23266 7 32 EV EV 23266 7 33 0.55 0.0253 23266 7 34 ENDCOMMON 3 0 23266 7 35 DATA 8 1 23266 7 36 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 7 37 ERR-5 ERR-SYS 23266 7 38 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 7 39 PER-CENT PER-CENT 23266 7 40 0.46 2.0 1.05 1.0 0.1 0.5 23266 7 41 0.55 1.65 23266 7 42 ENDDATA 6 0 23266 7 43 ENDSUBENT 42 0 23266 799999 SUBENT 23266008 20230215 231423266 8 1 BIB 5 11 23266 8 2 REACTION (12-MG-26(N,G)12-MG-27,,SIG,,AV) 23266 8 3 SIG-0 - the average thermal neutron cross-section . 23266 8 4 for neutrons at an average energy of E0=25.3 meV 23266 8 5 or velocity v0=2200 m/s. 23266 8 6 ANALYSIS Derived from directly measured data. 23266 8 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 8 8 Uncertainty on exp. SIG-0 value comes from to the 23266 8 9 observed SD between gamma-lines. 23266 8 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 8 11 (DEP,23266009) Directly measured data. 23266 8 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 8 13 ENDBIB 11 0 23266 8 14 COMMON 1 3 23266 8 15 EN 23266 8 16 EV 23266 8 17 0.0253 23266 8 18 ENDCOMMON 3 0 23266 8 19 DATA 2 1 23266 8 20 DATA DATA-ERR 23266 8 21 B B 23266 8 22 0.03718 0.00016 23266 8 23 ENDDATA 3 0 23266 8 24 ENDSUBENT 23 0 23266 899999 SUBENT 23266009 20141210 224123266 9 1 BIB 8 25 23266 9 2 REACTION (12-MG-26(N,G)12-MG-27,,SIG) 23266 9 3 Directly measured thermal neutron cross-section SIG-0 23266 9 4 SAMPLE - Provider - Goodfellow 23266 9 5 Matrix - Foil 23266 9 6 Elemental content, % weight - >99.99 23266 9 7 Average sample thickness, mm - 0.1 23266 9 8 (12-MG-26,NAT=0.1101) 11.01+-0.03 % 23266 9 9 DECAY-DATA ((1.)12-MG-27,9.462MIN,DG,170.7,0.0086) 23266 9 10 ((2.)12-MG-27,9.462MIN,DG,843.8,0.7180) reference line 23266 9 11 ((3.)12-MG-27,9.462MIN,DG,1014.4,0.2820) 23266 9 12 METHOD Measurement at channel S84 . 23266 9 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 9 14 extrapolated with aid of the k0-definition, atomic 23266 9 15 weight, isotopic composition, the gamma intensities 23266 9 16 values. 23266 9 17 Defined according to their ADS(activation decay scheme,23266 9 18 including decay branching factors). 23266 9 19 ADD-RES Measured k0-values with one-sigma uncertainty 23266 9 20 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 9 21 170.7 3.02E-6 (+-1.2%) 23266 9 22 843.8 2.54E-4 (+-0.8%) 23266 9 23 1014.4 9.90E-5 (+-0.7%) 23266 9 24 ERR-ANALYS Uncertainty is not given. 23266 9 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 9 26 (COREL,23266008) Average data 23266 9 27 ENDBIB 25 0 23266 9 28 COMMON 1 3 23266 9 29 EN 23266 9 30 EV 23266 9 31 0.0253 23266 9 32 ENDCOMMON 3 0 23266 9 33 DATA 2 3 23266 9 34 DATA DECAY-FLAG 23266 9 35 B NO-DIM 23266 9 36 0.03709 1. 23266 9 37 0.03737 2. 23266 9 38 0.03708 3. 23266 9 39 ENDDATA 5 0 23266 9 40 ENDSUBENT 39 0 23266 999999 SUBENT 23266010 20230215 231423266 10 1 BIB 8 17 23266 10 2 REACTION ((13-AL-27(N,G)13-AL-28,,RI,,AV)// 23266 10 3 (13-AL-27(N,G)13-AL-28,,SIG,,AV)) 23266 10 4 Q0 value (ratio of resonance integral to thermal 23266 10 5 neutron activation cross-section) 23266 10 6 SAMPLE - Provider - Goodfellow IRMM 23266 10 7 Matrix - Foil Al allo23266 10 8 Elemental content, % weight - >99.99 23266 10 9 Average sample thickness, mm - 0.015 0.1 23266 10 10 (13-AL-27,NAT=1.00) 23266 10 11 METHOD Measurement at channel S84 23266 10 12 DECAY-DATA (13-AL-28,2.2414MIN,DG,1778.9,1.0000) reference line 23266 10 13 ANALYSIS The Q0 factor was determined by 23266 10 14 - the classical method. 23266 10 15 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 10 16 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 10 17 (DEP,23266011) Directly measured data. 23266 10 18 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 10 19 ENDBIB 17 0 23266 10 20 COMMON 2 3 23266 10 21 EN-MIN-NM EN-DN 23266 10 22 EV EV 23266 10 23 0.55 0.0253 23266 10 24 ENDCOMMON 3 0 23266 10 25 DATA 2 1 23266 10 26 DATA DATA-ERR 23266 10 27 NO-DIM PER-CENT 23266 10 28 0.54 1.5 23266 10 29 ENDDATA 3 0 23266 10 30 ENDSUBENT 29 0 23266 1099999 SUBENT 23266011 20180202 226823266 11 1 BIB 8 27 23266 11 2 REACTION ((13-AL-27(N,G)13-AL-28,,RI)// 23266 11 3 (13-AL-27(N,G)13-AL-28,,SIG)) 23266 11 4 Q0 value (ratio of resonance integral to thermal 23266 11 5 neutron activation cross-section) 23266 11 6 SAMPLE - Provider - Goodfellow IRMM 23266 11 7 Matrix - Foil Al alloys23266 11 8 Elemental content, % weight - >99.99 23266 11 9 Average sample thickness, mm - 0.015 0.1 23266 11 10 (13-AL-27,NAT=1.00) 23266 11 11 METHOD Measurement at channel S84 23266 11 12 DECAY-DATA (13-AL-28,2.2414MIN,DG,1778.9,1.0000) reference line 23266 11 13 ANALYSIS The Q0 factor was determined by the classical method 23266 11 14 when inputting effective resonance energy factors 23266 11 15 from the literature. 23266 11 16 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 11 17 uncertainties ( 1 sigma) from: 23266 11 18 (ERR-1) alpha factor, 23266 11 19 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 11 20 epithermal flux for gold, 23266 11 21 (ERR-3) effective resonance energy Er, 23266 11 22 (ERR-4) Cd transmission factor FCd 23266 11 23 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 11 24 bare and Cd-covered sample. 23266 11 25 (ERR-S) Standard deviation. 23266 11 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 11 27 (COREL,23266010) Average data . 23266 11 28 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 11 29 ENDBIB 27 0 23266 11 30 COMMON 2 3 23266 11 31 EN-MIN-NM EN-DN 23266 11 32 EV EV 23266 11 33 0.55 0.0253 23266 11 34 ENDCOMMON 3 0 23266 11 35 DATA 8 1 23266 11 36 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 11 37 ERR-5 ERR-SYS 23266 11 38 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 11 39 PER-CENT PER-CENT 23266 11 40 0.54 1.5 1.05 1.0 0.1 0.5 23266 11 41 0.55 1.65 23266 11 42 ENDDATA 6 0 23266 11 43 ENDSUBENT 42 0 23266 1199999 SUBENT 23266012 20230215 231423266 12 1 BIB 5 11 23266 12 2 REACTION (13-AL-27(N,G)13-AL-28,,SIG,,AV) 23266 12 3 SIG-0 - the average thermal neutron cross-section . 23266 12 4 for neutrons at an average energy of E0=25.3 meV 23266 12 5 or velocity v0=2200 m/s. 23266 12 6 ANALYSIS Derived from directly measured data. 23266 12 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 12 8 Uncertainty on exp. SIG-0 value comes from to the 23266 12 9 observed SD between gamma-lines. 23266 12 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 12 11 (DEP,23266013) Directly measured data. 23266 12 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 12 13 ENDBIB 11 0 23266 12 14 COMMON 1 3 23266 12 15 EN 23266 12 16 EV 23266 12 17 0.0253 23266 12 18 ENDCOMMON 3 0 23266 12 19 DATA 2 1 23266 12 20 DATA DATA-ERR 23266 12 21 B B 23266 12 22 0.2298 0.0023 23266 12 23 ENDDATA 3 0 23266 12 24 ENDSUBENT 23 0 23266 1299999 SUBENT 23266013 20141210 224123266 13 1 BIB 8 21 23266 13 2 REACTION (13-AL-27(N,G)13-AL-28,,SIG) 23266 13 3 Directly measured thermal neutron cross-section SIG-0 23266 13 4 SAMPLE - Provider - Goodfellow IRMM 23266 13 5 Matrix - Foil Al alloys23266 13 6 Elemental content, % weight - >99.99 23266 13 7 Average sample thickness, mm - 0.015 0.1 23266 13 8 (13-AL-27,NAT=1.00) 23266 13 9 DECAY-DATA (13-AL-28,2.2414MIN,DG,1778.9,1.0000) reference line 23266 13 10 METHOD Measurement at channel S84 . 23266 13 11 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 13 12 extrapolated with aid of the k0-definition, atomic 23266 13 13 weight, isotopic composition, the gamma intensities 23266 13 14 values. 23266 13 15 Defined according to their ADS(activation decay scheme,23266 13 16 including decay branching factors). 23266 13 17 ADD-RES Measured k0-values with one-sigma uncertainty 23266 13 18 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 13 19 1778.9 1.77E-2 (+-2.0%) 23266 13 20 ERR-ANALYS Uncertainty is not given. 23266 13 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 13 22 (COREL,23266012) Average data 23266 13 23 ENDBIB 21 0 23266 13 24 COMMON 1 3 23266 13 25 EN 23266 13 26 EV 23266 13 27 0.0253 23266 13 28 ENDCOMMON 3 0 23266 13 29 DATA 1 1 23266 13 30 DATA 23266 13 31 B 23266 13 32 0.22981 23266 13 33 ENDDATA 3 0 23266 13 34 ENDSUBENT 33 0 23266 1399999 SUBENT 23266014 20230215 231423266 14 1 BIB 8 17 23266 14 2 REACTION ((17-CL-37(N,G)17-CL-38,,RI,,AV)// 23266 14 3 (17-CL-37(N,G)17-CL-38,,SIG,,AV)) 23266 14 4 Q0 value (ratio of resonance integral to thermal 23266 14 5 neutron activation cross-section) 23266 14 6 SAMPLE - Provider - Fluka 23266 14 7 Matrix - High purity NaCl 23266 14 8 Elemental content, % weight - 60.680 23266 14 9 Average sample thickness, mm - 0.15 23266 14 10 (17-CL-37,NAT=0.2424) 24.24+-0.10 % 23266 14 11 METHOD Measurement at channel S84 23266 14 12 DECAY-DATA (17-CL-38-G,37.24MIN,DG,1642.7,0.333,DG,2167.4,0.444) 23266 14 13 ANALYSIS The Q0 factor was determined by 23266 14 14 - the classical method. 23266 14 15 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 14 16 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 14 17 (DEP,23266015) Directly measured data . 23266 14 18 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 14 19 ENDBIB 17 0 23266 14 20 COMMON 2 3 23266 14 21 EN-MIN-NM EN-DN 23266 14 22 EV EV 23266 14 23 0.55 0.0253 23266 14 24 ENDCOMMON 3 0 23266 14 25 DATA 2 1 23266 14 26 DATA DATA-ERR 23266 14 27 NO-DIM PER-CENT 23266 14 28 0.48 1.5 23266 14 29 ENDDATA 3 0 23266 14 30 ENDSUBENT 29 0 23266 1499999 SUBENT 23266015 20141210 224123266 15 1 BIB 7 26 23266 15 2 REACTION ((17-CL-37(N,G)17-CL-38,,RI)// 23266 15 3 (17-CL-37(N,G)17-CL-38,,SIG)) 23266 15 4 Q0 value (ratio of resonance integral to thermal 23266 15 5 neutron activation cross-section) 23266 15 6 SAMPLE - Provider - Fluka 23266 15 7 Matrix - High purity NaCl 23266 15 8 Elemental content, % weight - 60.680 23266 15 9 Average sample thickness, mm - 0.15 23266 15 10 (17-CL-37,NAT=0.2424) 24.24+-0.10 % 23266 15 11 METHOD Measurement at channel S84 23266 15 12 DECAY-DATA (17-CL-38-G,37.24MIN,DG,1642.7,0.333,DG,2167.4,0.444) 23266 15 13 ANALYSIS The Q0 factor was determined by the classical method 23266 15 14 when inputting effective resonance energy factors 23266 15 15 from the literature. 23266 15 16 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 15 17 uncertainties ( 1 sigma) from: 23266 15 18 (ERR-1) alpha factor, 23266 15 19 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 15 20 epithermal flux for gold, 23266 15 21 (ERR-3) effective resonance energy Er, 23266 15 22 (ERR-4) Cd transmission factor FCd 23266 15 23 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 15 24 bare and Cd-covered sample. 23266 15 25 (ERR-S) Standard deviation. 23266 15 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 15 27 (COREL,23266014) Average data . 23266 15 28 ENDBIB 26 0 23266 15 29 COMMON 2 3 23266 15 30 EN-MIN-NM EN-DN 23266 15 31 EV EV 23266 15 32 0.55 0.0253 23266 15 33 ENDCOMMON 3 0 23266 15 34 DATA 8 1 23266 15 35 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 15 36 ERR-5 ERR-SYS 23266 15 37 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 15 38 PER-CENT PER-CENT 23266 15 39 0.48 3.0 1.0 1.05 0.1 0.5 23266 15 40 0.55 1.65 23266 15 41 ENDDATA 6 0 23266 15 42 ENDSUBENT 41 0 23266 1599999 SUBENT 23266016 20230215 231423266 16 1 BIB 5 11 23266 16 2 REACTION (17-CL-37(N,G)17-CL-38,,SIG,,AV) 23266 16 3 SIG-0 - the average thermal neutron cross-section . 23266 16 4 for neutrons at an average energy of E0=25.3 meV 23266 16 5 or velocity v0=2200 m/s. 23266 16 6 ANALYSIS Derived from directly measured data. 23266 16 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 16 8 Uncertainty on exp. SIG-0 value comes from to the 23266 16 9 observed SD between gamma-lines. 23266 16 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 16 11 (DEP,23266017) Directly measured data. 23266 16 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 16 13 ENDBIB 11 0 23266 16 14 COMMON 1 3 23266 16 15 EN 23266 16 16 EV 23266 16 17 0.0253 23266 16 18 ENDCOMMON 3 0 23266 16 19 DATA 2 1 23266 16 20 DATA DATA-ERR 23266 16 21 B B 23266 16 22 0.412 0.003 23266 16 23 ENDDATA 3 0 23266 16 24 ENDSUBENT 23 0 23266 1699999 SUBENT 23266017 20141210 224123266 17 1 BIB 8 23 23266 17 2 REACTION (17-CL-37(N,G)17-CL-38,,SIG) 23266 17 3 Directly measured thermal neutron cross-section SIG-0 23266 17 4 SAMPLE - Provider - Fluka 23266 17 5 Matrix - High purity NaCl 23266 17 6 Elemental content, % weight - 60.680 23266 17 7 Average sample thickness, mm - 0.15 23266 17 8 (17-CL-37,NAT=0.2424) 24.24+-0.10 % 23266 17 9 DECAY-DATA ((1.)17-CL-38-G,37.24MIN,DG,1642.7,0.333) 23266 17 10 ((2.)17-CL-38-G,37.24MIN,DG,2167.4,0.444) 23266 17 11 METHOD Measurement at channel S84 . 23266 17 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 17 13 extrapolated with aid of the k0-definition, atomic 23266 17 14 weight, isotopic composition, the gamma intensities 23266 17 15 values. 23266 17 16 Defined according to their ADS(activation decay scheme,23266 17 17 including decay branching factors). 23266 17 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266 17 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 17 20 1642.7 1.95E-3 (+-1.5%) 23266 17 21 2167.4 2.63E-3 (+-1.5%) 23266 17 22 ERR-ANALYS Uncertainty is not given. 23266 17 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 17 24 (COREL,23266016) Average data 23266 17 25 ENDBIB 23 0 23266 17 26 COMMON 1 3 23266 17 27 EN 23266 17 28 EV 23266 17 29 0.0253 23266 17 30 ENDCOMMON 3 0 23266 17 31 DATA 2 2 23266 17 32 DATA DECAY-FLAG 23266 17 33 B NO-DIM 23266 17 34 0.410 1. 23266 17 35 0.415 2. 23266 17 36 ENDDATA 4 0 23266 17 37 ENDSUBENT 36 0 23266 1799999 SUBENT 23266018 20230215 231423266 18 1 BIB 9 27 23266 18 2 REACTION 1((21-SC-45(N,G)21-SC-46,,RI,,AV)// 23266 18 3 (21-SC-45(N,G)21-SC-46,,SIG,,AV)) 23266 18 4 2((21-SC-45(N,G)21-SC-46,,RI)// 23266 18 5 (21-SC-45(N,G)21-SC-46,,SIG)) 23266 18 6 Q0 value (ratio of resonance integral to thermal 23266 18 7 neutron activation cross-section) 23266 18 8 SAMPLE - Provider - IRMM 23266 18 9 Matrix - Foil,Al alloy 23266 18 10 Elemental content, % weight - 1. 23266 18 11 Average sample thickness, mm - 0.1 23266 18 12 (21-SC-45,NAT=1.00) 23266 18 13 METHOD Measurement at channels S84, Y4,X26. 23266 18 14 DECAY-DATA (21-SC-46-M,18.75SEC) 23266 18 15 (21-SC-46-G,83.8D,DG,889.3,0.99984,DG,1120.5,0.99987) 23266 18 16 ANALYSIS The Q0 factor was determined by 23266 18 17 1- the classical method: through the weighted mean and 23266 18 18 observed standard deviation of the 3 irradiation 23266 18 19 channels employed (S84, Y4, X26), when inputting Er 23266 18 20 factors from the literature. 23266 18 21 2- the a-vector method: through the parameters 23266 18 22 (m, b) --> determination of the value as well. 23266 18 23 ADD-RES Effective resonance Energy was defined by a-vect23266 18 24 method to be 0.00 eV. 23266 18 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 18 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 18 27 1(DEP,23266019) Directly measured data . 23266 18 28 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 18 29 ENDBIB 27 0 23266 18 30 COMMON 2 3 23266 18 31 EN-MIN-NM EN-DN 23266 18 32 EV EV 23266 18 33 0.55 0.0253 23266 18 34 ENDCOMMON 3 0 23266 18 35 DATA 4 1 23266 18 36 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 18 37 NO-DIM PER-CENT NO-DIM PER-CENT 23266 18 38 0.45 8. 0.44 1.5 23266 18 39 ENDDATA 3 0 23266 18 40 ENDSUBENT 39 0 23266 1899999 SUBENT 23266019 20141210 224123266 19 1 BIB 7 30 23266 19 2 REACTION ((21-SC-45(N,G)21-SC-46,,RI)// 23266 19 3 (21-SC-45(N,G)21-SC-46,,SIG)) 23266 19 4 Q0 value (ratio of resonance integral to thermal 23266 19 5 neutron activation cross-section) 23266 19 6 SAMPLE - Provider - IRMM 23266 19 7 Matrix - Foil,Al alloy 23266 19 8 Elemental content, % weight - 1. 23266 19 9 Average sample thickness, mm - 0.1 23266 19 10 (21-SC-45,NAT=1.00) 23266 19 11 DECAY-DATA (21-SC-46-M,18.75SEC) 23266 19 12 (21-SC-46-G,83.8D,DG,889.3,0.99984,DG,1120.5,0.99987) 23266 19 13 FLAG Measurement at channels: 23266 19 14 (1.) S84, 23266 19 15 (2.) Y4, 23266 19 16 (3.) X26 . 23266 19 17 ANALYSIS The Q0 factor was determined by the classical method 23266 19 18 when inputting effective resonance energy factors 23266 19 19 from the literature. 23266 19 20 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 19 21 uncertainties ( 1 sigma) from: 23266 19 22 (ERR-1) alpha factor, 23266 19 23 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 19 24 epithermal flux for gold, 23266 19 25 (ERR-3) effective resonance energy Er, 23266 19 26 (ERR-4) Cd transmission factor FCd 23266 19 27 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 19 28 bare and Cd-covered sample. 23266 19 29 (ERR-S) Standard deviation. 23266 19 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 19 31 (COREL,23266018) Average data . 23266 19 32 ENDBIB 30 0 23266 19 33 COMMON 2 3 23266 19 34 EN-MIN-NM EN-DN 23266 19 35 EV EV 23266 19 36 0.55 0.0253 23266 19 37 ENDCOMMON 3 0 23266 19 38 DATA 9 3 23266 19 39 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 19 40 ERR-5 ERR-SYS FLAG 23266 19 41 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 19 42 PER-CENT PER-CENT NO-DIM 23266 19 43 0.42 0.3 0.05 1.05 0.0 0.5 23266 19 44 0.5 1.25 1. 23266 19 45 0.49 0.25 0.25 1.4 0.0 0.6 23266 19 46 0.8 1.75 2. 23266 19 47 0.50 0.35 1.25 1.8 0.0 0.55 23266 19 48 1.0 2.45 3. 23266 19 49 ENDDATA 10 0 23266 19 50 ENDSUBENT 49 0 23266 1999999 SUBENT 23266020 20230215 231423266 20 1 BIB 5 11 23266 20 2 REACTION (21-SC-45(N,G)21-SC-46,,SIG,,AV) 23266 20 3 SIG-0 - the average thermal neutron cross-section . 23266 20 4 for neutrons at an average energy of E0=25.3 meV 23266 20 5 or velocity v0=2200 m/s. 23266 20 6 ANALYSIS Derived from directly measured data. 23266 20 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 20 8 Uncertainty on exp. SIG-0 value comes from to the 23266 20 9 observed SD between gamma-lines. 23266 20 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 20 11 (DEP,23266021) Directly measured data. 23266 20 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 20 13 ENDBIB 11 0 23266 20 14 COMMON 1 3 23266 20 15 EN 23266 20 16 EV 23266 20 17 0.0253 23266 20 18 ENDCOMMON 3 0 23266 20 19 DATA 2 1 23266 20 20 DATA DATA-ERR 23266 20 21 B B 23266 20 22 26.9 0.1 23266 20 23 ENDDATA 3 0 23266 20 24 ENDSUBENT 23 0 23266 2099999 SUBENT 23266021 20141210 224123266 21 1 BIB 8 26 23266 21 2 REACTION (21-SC-45(N,G)21-SC-46,,SIG) 23266 21 3 Directly measured thermal neutron cross-section SIG-0 23266 21 4 SAMPLE - Provider - IRMM 23266 21 5 Matrix - Foil,Al alloy 23266 21 6 Elemental content, % weight - 1. 23266 21 7 Average sample thickness, mm - 0.1 23266 21 8 (21-SC-45,NAT=1.00) 23266 21 9 DECAY-DATA (21-SC-46-M,18.75SEC) 23266 21 10 ((1.)21-SC-46-G,83.8D,DG,889.3,0.99984) 23266 21 11 ((2.)21-SC-46-G,83.8D,DG,1120.5,0.99987) reference line23266 21 12 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 21 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 21 14 extrapolated with aid of the k0-definition, atomic 23266 21 15 weight, isotopic composition, the gamma intensities 23266 21 16 values. 23266 21 17 Defined according to their ADS(activation decay scheme,23266 21 18 including decay branching factors). 23266 21 19 ADD-RES Measured k0-values with one-sigma uncertainty 23266 21 20 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 21 21 889.3 1.25E-0 (+-0.4%) 23266 21 22 1120.5 1.25E-0 (+-0.4%) 23266 21 23 Effective resonance energy defined by a-vector 23266 21 24 method 0.00 eV. 23266 21 25 ERR-ANALYS Uncertainty is not given. 23266 21 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 21 27 (COREL,23266020) Average data 23266 21 28 ENDBIB 26 0 23266 21 29 COMMON 1 3 23266 21 30 EN 23266 21 31 EV 23266 21 32 0.0253 23266 21 33 ENDCOMMON 3 0 23266 21 34 DATA 2 2 23266 21 35 DATA DECAY-FLAG 23266 21 36 B NO-DIM 23266 21 37 27.0 1. 23266 21 38 26.8 2. 23266 21 39 ENDDATA 4 0 23266 21 40 ENDSUBENT 39 0 23266 2199999 SUBENT 23266022 20230215 231423266 22 1 BIB 8 17 23266 22 2 REACTION ((22-TI-50(N,G)22-TI-51,,RI,,AV)// 23266 22 3 (22-TI-50(N,G)22-TI-51,,SIG,,AV)) 23266 22 4 Q0 value (ratio of resonance integral to thermal 23266 22 5 neutron activation cross-section) 23266 22 6 SAMPLE - Provider - CBNM 23266 22 7 Matrix - Foil 23266 22 8 Elemental content, % weight - >99.99 23266 22 9 Average sample thickness, mm - 0.1 23266 22 10 (22-TI-50,NAT=0.0518) 5.18+-0.02 % 23266 22 11 METHOD Measurement at channel S84 23266 22 12 DECAY-DATA (22-TI-51,5.76MIN,DG,320.1,0.9310,DG,928.0,0.0619) 23266 22 13 ANALYSIS The Q0 factor was determined by 23266 22 14 - the classical method. 23266 22 15 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 22 16 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 22 17 (DEP,23266023) Directly measured data . 23266 22 18 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 22 19 ENDBIB 17 0 23266 22 20 COMMON 2 3 23266 22 21 EN-MIN-NM EN-DN 23266 22 22 EV EV 23266 22 23 0.55 0.0253 23266 22 24 ENDCOMMON 3 0 23266 22 25 DATA 2 1 23266 22 26 DATA DATA-ERR 23266 22 27 NO-DIM PER-CENT 23266 22 28 0.52 1.5 23266 22 29 ENDDATA 3 0 23266 22 30 ENDSUBENT 29 0 23266 2299999 SUBENT 23266023 20141210 224123266 23 1 BIB 7 26 23266 23 2 REACTION ((22-TI-50(N,G)22-TI-51,,RI)// 23266 23 3 (22-TI-50(N,G)22-TI-51,,SIG)) 23266 23 4 Q0 value (ratio of resonance integral to thermal 23266 23 5 neutron activation cross-section) 23266 23 6 SAMPLE - Provider - CBNM 23266 23 7 Matrix - Foil 23266 23 8 Elemental content, % weight - >99.99 23266 23 9 Average sample thickness, mm - 0.1 23266 23 10 (22-TI-50,NAT=0.0518) 5.18+-0.02 % 23266 23 11 METHOD Measurement at channel S84 23266 23 12 DECAY-DATA (22-TI-51,5.76MIN,DG,320.1,0.9310,DG,928.0,0.0619) 23266 23 13 ANALYSIS The Q0 factor was determined by the classical method 23266 23 14 when inputting effective resonance energy factors 23266 23 15 from the literature. 23266 23 16 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 23 17 uncertainties ( 1 sigma) from: 23266 23 18 (ERR-1) alpha factor, 23266 23 19 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 23 20 epithermal flux for gold, 23266 23 21 (ERR-3) effective resonance energy Er, 23266 23 22 (ERR-4) Cd transmission factor FCd 23266 23 23 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 23 24 bare and Cd-covered sample. 23266 23 25 (ERR-S) Standard deviation. 23266 23 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 23 27 (COREL,23266022) Average data . 23266 23 28 ENDBIB 26 0 23266 23 29 COMMON 2 3 23266 23 30 EN-MIN-NM EN-DN 23266 23 31 EV EV 23266 23 32 0.55 0.0253 23266 23 33 ENDCOMMON 3 0 23266 23 34 DATA 8 1 23266 23 35 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 23 36 ERR-5 ERR-SYS 23266 23 37 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 23 38 PER-CENT PER-CENT 23266 23 39 0.52 1.0 1.05 1.0 0.1 0.5 23266 23 40 0.55 1.65 23266 23 41 ENDDATA 6 0 23266 23 42 ENDSUBENT 41 0 23266 2399999 SUBENT 23266024 20230215 231423266 24 1 BIB 5 11 23266 24 2 REACTION (22-TI-50(N,G)22-TI-51,,SIG,,AV) 23266 24 3 SIG-0 - the average thermal neutron cross-section . 23266 24 4 for neutrons at an average energy of E0=25.3 meV 23266 24 5 or velocity v0=2200 m/s. 23266 24 6 ANALYSIS Derived from directly measured data. 23266 24 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 24 8 Uncertainty on exp. SIG-0 value comes from to the 23266 24 9 observed SD between gamma-lines. 23266 24 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 24 11 (DEP,23266025) Directly measured data. 23266 24 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 24 13 ENDBIB 11 0 23266 24 14 COMMON 1 3 23266 24 15 EN 23266 24 16 EV 23266 24 17 0.0253 23266 24 18 ENDCOMMON 3 0 23266 24 19 DATA 2 1 23266 24 20 DATA DATA-ERR 23266 24 21 B B 23266 24 22 0.1725 0.0046 23266 24 23 ENDDATA 3 0 23266 24 24 ENDSUBENT 23 0 23266 2499999 SUBENT 23266025 20141210 224123266 25 1 BIB 8 23 23266 25 2 REACTION (22-TI-50(N,G)22-TI-51,,SIG) 23266 25 3 Directly measured thermal neutron cross-section SIG-0 23266 25 4 SAMPLE - Provider - CBNM 23266 25 5 Matrix - Foil 23266 25 6 Elemental content, % weight - >99.99 23266 25 7 Average sample thickness, mm - 0.1 23266 25 8 (22-TI-50,NAT=0.0518) 5.18+-0.02 % 23266 25 9 DECAY-DATA ((1.)22-TI-51,5.76MIN,DG,320.1,0.9310) 23266 25 10 ((2.)22-TI-51,5.76MIN,DG,928.0,0.0619) 23266 25 11 METHOD Measurement at channel S84 . 23266 25 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 25 13 extrapolated with aid of the k0-definition, atomic 23266 25 14 weight, isotopic composition, the gamma intensities 23266 25 15 values. 23266 25 16 Defined according to their ADS(activation decay scheme,23266 25 17 including decay branching factors). 23266 25 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266 25 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 25 20 320.1 3.70E-4 (+-1.0%) 23266 25 21 928.0 2.64E-5 (+-1.5%) 23266 25 22 ERR-ANALYS Uncertainty is not given. 23266 25 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 25 24 (COREL,23266020) Average data 23266 25 25 ENDBIB 23 0 23266 25 26 COMMON 1 3 23266 25 27 EN 23266 25 28 EV 23266 25 29 0.0253 23266 25 30 ENDCOMMON 3 0 23266 25 31 DATA 2 2 23266 25 32 DATA DECAY-FLAG 23266 25 33 B NO-DIM 23266 25 34 0.1757 1. 23266 25 35 0.1692 2. 23266 25 36 ENDDATA 4 0 23266 25 37 ENDSUBENT 36 0 23266 2599999 SUBENT 23266026 20230215 231423266 26 1 BIB 7 16 23266 26 2 REACTION ((23-V-51(N,G)23-V-52,,RI,,AV)// 23266 26 3 (23-V-51(N,G)23-V-52,,SIG,,AV)) 23266 26 4 Q0 value (ratio of resonance integral to thermal 23266 26 5 neutron activation cross-section) 23266 26 6 SAMPLE - Provider - CBNM 23266 26 7 Matrix - Foil 23266 26 8 Elemental content, % weight - >99.99 23266 26 9 Average sample thickness, mm - 0.1 23266 26 10 (23-V-51,ENR=0.9975) 99.75+-0.04 % 23266 26 11 DECAY-DATA (23-V-52,3.75MIN,DG,1434.0,1.000) 23266 26 12 ANALYSIS The Q0 factor was determined by 23266 26 13 - the classical method. 23266 26 14 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 26 15 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 26 16 (DEP,23266027) Directly measured data . 23266 26 17 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 26 18 ENDBIB 16 0 23266 26 19 COMMON 2 3 23266 26 20 EN-MIN-NM EN-DN 23266 26 21 EV EV 23266 26 22 0.55 0.0253 23266 26 23 ENDCOMMON 3 0 23266 26 24 DATA 2 1 23266 26 25 DATA DATA-ERR 23266 26 26 NO-DIM PER-CENT 23266 26 27 0.55 1.5 23266 26 28 ENDDATA 3 0 23266 26 29 ENDSUBENT 28 0 23266 2699999 SUBENT 23266027 20141210 224123266 27 1 BIB 7 26 23266 27 2 REACTION ((23-V-51(N,G)23-V-52,,RI)// 23266 27 3 (23-V-51(N,G)23-V-52,,SIG)) 23266 27 4 Q0 value (ratio of resonance integral to thermal 23266 27 5 neutron activation cross-section) 23266 27 6 SAMPLE - Provider - CBNM 23266 27 7 Matrix - Foil 23266 27 8 Elemental content, % weight - >99.99 23266 27 9 Average sample thickness, mm - 0.1 23266 27 10 (23-V-51,ENR=0.9975) 99.75+-0.04 % 23266 27 11 METHOD Measurement at channel S84 23266 27 12 DECAY-DATA (23-V-52,3.75MIN,DG,1434.0,1.000) 23266 27 13 ANALYSIS The Q0 factor was determined by the classical method 23266 27 14 when inputting effective resonance energy factors 23266 27 15 from the literature. 23266 27 16 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 27 17 uncertainties ( 1 sigma) from: 23266 27 18 (ERR-1) alpha factor, 23266 27 19 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 27 20 epithermal flux for gold, 23266 27 21 (ERR-3) effective resonance energy Er, 23266 27 22 (ERR-4) Cd transmission factor FCd 23266 27 23 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 27 24 bare and Cd-covered sample. 23266 27 25 (ERR-S) Standard deviation. 23266 27 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 27 27 (COREL,23266026) Average data . 23266 27 28 ENDBIB 26 0 23266 27 29 COMMON 2 3 23266 27 30 EN-MIN-NM EN-DN 23266 27 31 EV EV 23266 27 32 0.55 0.0253 23266 27 33 ENDCOMMON 3 0 23266 27 34 DATA 8 1 23266 27 35 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 27 36 ERR-5 ERR-SYS 23266 27 37 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 27 38 PER-CENT PER-CENT 23266 27 39 0.55 2.0 1.05 1.0 0.1 0.5 23266 27 40 0.55 1.65 23266 27 41 ENDDATA 6 0 23266 27 42 ENDSUBENT 41 0 23266 2799999 SUBENT 23266028 20230215 231423266 28 1 BIB 5 11 23266 28 2 REACTION (23-V-51(N,G)23-V-52,,SIG,,AV) 23266 28 3 SIG-0 - the average thermal neutron cross-section . 23266 28 4 for neutrons at an average energy of E0=25.3 meV 23266 28 5 or velocity v0=2200 m/s. 23266 28 6 ANALYSIS Derived from directly measured data. 23266 28 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 28 8 Uncertainty on exp. SIG-0 value comes from to the 23266 28 9 observed SD between gamma-lines. 23266 28 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 28 11 (DEP,23266029) Directly measured data. 23266 28 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 28 13 ENDBIB 11 0 23266 28 14 COMMON 1 3 23266 28 15 EN 23266 28 16 EV 23266 28 17 0.0253 23266 28 18 ENDCOMMON 3 0 23266 28 19 DATA 2 1 23266 28 20 DATA DATA-ERR 23266 28 21 B B 23266 28 22 4.77 0.05 23266 28 23 ENDDATA 3 0 23266 28 24 ENDSUBENT 23 0 23266 2899999 SUBENT 23266029 20141210 224123266 29 1 BIB 8 21 23266 29 2 REACTION (23-V-51(N,G)23-V-52,,SIG) 23266 29 3 Directly measured thermal neutron cross-section SIG-0 23266 29 4 SAMPLE - Provider - CBNM 23266 29 5 Matrix - Foil 23266 29 6 Elemental content, % weight - >99.99 23266 29 7 Average sample thickness, mm - 0.1 23266 29 8 (23-V-51,ENR=0.9975) 99.75+-0.04 % 23266 29 9 DECAY-DATA (23-V-52,3.75MIN,DG,1434.0,1.000) 23266 29 10 METHOD Measurement at channel S84 . 23266 29 11 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 29 12 extrapolated with aid of the k0-definition, atomic 23266 29 13 weight, isotopic composition, the gamma intensities 23266 29 14 values. 23266 29 15 Defined according to their ADS(activation decay scheme,23266 29 16 including decay branching factors). 23266 29 17 ADD-RES Measured k0-values with one-sigma uncertainty 23266 29 18 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 29 19 31434.0 1.96E-1 (+-1.1%) 23266 29 20 ERR-ANALYS Uncertainty is not given. 23266 29 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 29 22 (COREL,23266028) Average data 23266 29 23 ENDBIB 21 0 23266 29 24 COMMON 1 3 23266 29 25 EN 23266 29 26 EV 23266 29 27 0.0253 23266 29 28 ENDCOMMON 3 0 23266 29 29 DATA 1 1 23266 29 30 DATA 23266 29 31 B 23266 29 32 4.77 23266 29 33 ENDDATA 3 0 23266 29 34 ENDSUBENT 33 0 23266 2999999 SUBENT 23266030 20230215 231423266 30 1 BIB 10 31 23266 30 2 REACTION 1((25-MN-55(N,G)25-MN-56,,RI,,AV)// 23266 30 3 (25-MN-55(N,G)25-MN-56,,SIG,,AV)) 23266 30 4 2((25-MN-55(N,G)25-MN-56,,RI)// 23266 30 5 (25-MN-55(N,G)25-MN-56,,SIG)) 23266 30 6 Q0 value (ratio of resonance integral to thermal 23266 30 7 neutron activation cross-section) 23266 30 8 SAMPLE - Provider - IRMM 23266 30 9 Matrix - Foil,Al alloy 23266 30 10 Elemental content, % weight - 1. 23266 30 11 Average sample thickness, mm - 0.1 23266 30 12 (25-MN-55,NAT=1.00) 23266 30 13 METHOD Measurement at channels S84, X26. 23266 30 14 DECAY-DATA (25-MN-56,2.579HR,DG,846.8,0.9885,DG,1810.7,0.2690, 23266 30 15 DG,2113.1,0.1420) 23266 30 16 ANALYSIS The Q0 factor was determined by 23266 30 17 1- the classical method: through the weighted mean and 23266 30 18 observed standard deviation of the 3 irradiation 23266 30 19 channels employed (S84, X26), when inputting Er 23266 30 20 factors from the literature. 23266 30 21 2- the a-vector method: through the parameters 23266 30 22 (m, b) --> determination of the value as well. 23266 30 23 ADD-RES Effective resonance Energy was defined by a-vect23266 30 24 method to be 341.eV ( +-8%, 2sigma). 23266 30 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 30 26 COMMENT Of compiler M.M. 23266 30 27 There are misprints in Suppl.material 23266 30 28 10967-2012-2132-MOESM2-ESM.pdf: 23266 30 29 Target Mn-54 -> Mn-55, Formed isotope Mn-55 -> Mn-56. 23266 30 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 30 31 1(DEP,23266031) Directly measured data . 23266 30 32 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 30 33 ENDBIB 31 0 23266 30 34 COMMON 2 3 23266 30 35 EN-MIN-NM EN-DN 23266 30 36 EV EV 23266 30 37 0.55 0.0253 23266 30 38 ENDCOMMON 3 0 23266 30 39 DATA 4 1 23266 30 40 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 30 41 NO-DIM PER-CENT NO-DIM PER-CENT 23266 30 42 1.04 1. 1.03 2. 23266 30 43 ENDDATA 3 0 23266 30 44 ENDSUBENT 43 0 23266 3099999 SUBENT 23266031 20141210 224123266 31 1 BIB 7 29 23266 31 2 REACTION ((25-MN-55(N,G)25-MN-56,,RI)// 23266 31 3 (25-MN-55(N,G)25-MN-56,,SIG)) 23266 31 4 Q0 value (ratio of resonance integral to thermal 23266 31 5 neutron activation cross-section) 23266 31 6 SAMPLE - Provider - IRMM 23266 31 7 Matrix - Foil,Al alloy 23266 31 8 Elemental content, % weight - 1. 23266 31 9 Average sample thickness, mm - 0.1 23266 31 10 (25-MN-55,NAT=1.00) 23266 31 11 DECAY-DATA (25-MN-56,2.579HR,DG,846.8,0.9885,DG,1810.7,0.2690, 23266 31 12 DG,2113.1,0.1420) 23266 31 13 FLAG Measurement at channels: 23266 31 14 (1.) S84, 23266 31 15 (2.) X26 . 23266 31 16 ANALYSIS The Q0 factor was determined by the classical method 23266 31 17 when inputting effective resonance energy factors 23266 31 18 from the literature. 23266 31 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 31 20 uncertainties ( 1 sigma) from: 23266 31 21 (ERR-1) alpha factor, 23266 31 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 31 23 epithermal flux for gold, 23266 31 24 (ERR-3) effective resonance energy Er, 23266 31 25 (ERR-4) Cd transmission factor FCd 23266 31 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 31 27 bare and Cd-covered sample. 23266 31 28 (ERR-S) Standard deviation. 23266 31 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 31 30 (COREL,23266030) Average data . 23266 31 31 ENDBIB 29 0 23266 31 32 COMMON 2 3 23266 31 33 EN-MIN-NM EN-DN 23266 31 34 EV EV 23266 31 35 0.55 0.0253 23266 31 36 ENDCOMMON 3 0 23266 31 37 DATA 9 2 23266 31 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 31 39 ERR-5 ERR-SYS FLAG 23266 31 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 31 41 PER-CENT PER-CENT NO-DIM 23266 31 42 1.03 1.45 0.9 1.05 0.1 0.6 23266 31 43 0.65 1.65 1. 23266 31 44 1.06 1.3 1.25 1.65 0.15 0.6 23266 31 45 0.65 2.25 2. 23266 31 46 ENDDATA 8 0 23266 31 47 ENDSUBENT 46 0 23266 3199999 SUBENT 23266032 20230215 231423266 32 1 BIB 4 10 23266 32 2 REACTION (25-MN-55(N,G)25-MN-56,,SIG,,AV) 23266 32 3 SIG-0 - the average thermal neutron cross-section . 23266 32 4 for neutrons at an average energy of E0=25.3 meV 23266 32 5 or velocity v0=2200 m/s. 23266 32 6 ANALYSIS Derived from directly measured data. 23266 32 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 32 8 Uncertainty on exp. SIG-0 value comes from to the 23266 32 9 observed SD between gamma-lines. 23266 32 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 32 11 (DEP,23266033) Directly measured data. 23266 32 12 ENDBIB 10 0 23266 32 13 COMMON 1 3 23266 32 14 EN 23266 32 15 EV 23266 32 16 0.0253 23266 32 17 ENDCOMMON 3 0 23266 32 18 DATA 2 1 23266 32 19 DATA DATA-ERR 23266 32 20 B B 23266 32 21 13.03 0.10 23266 32 22 ENDDATA 3 0 23266 32 23 ENDSUBENT 22 0 23266 3299999 SUBENT 23266033 20141210 224123266 33 1 BIB 8 27 23266 33 2 REACTION (25-MN-55(N,G)25-MN-56,,SIG) 23266 33 3 Directly measured thermal neutron cross-section SIG-0 23266 33 4 SAMPLE - Provider - IRMM 23266 33 5 Matrix - Foil,Al alloy 23266 33 6 Elemental content, % weight - 1. 23266 33 7 Average sample thickness, mm - 0.1 23266 33 8 (25-MN-55,NAT=1.00) 23266 33 9 DECAY-DATA ((1.)25-MN-56,2.579HR,DG,846.8,0.9885) 23266 33 10 ((2.)25-MN-56,2.579HR,DG,1810.7,0.2690) 23266 33 11 ((3.)25-MN-56,2.579HR,DG,2113.1,0.1420) 23266 33 12 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 33 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 33 14 extrapolated with aid of the k0-definition, atomic 23266 33 15 weight, isotopic composition, the gamma intensities 23266 33 16 values. 23266 33 17 Defined according to their ADS(activation decay scheme,23266 33 18 including decay branching factors). 23266 33 19 ADD-RES Measured k0-values with one-sigma uncertainty 23266 33 20 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 33 21 846.8 4.94E-1 (+-0.7%) 23266 33 22 1810.7 1.32E-1 (+-0.4%) 23266 33 23 2113.1 7.04E-2 (+-0.2%) 23266 33 24 Effective resonance energy defined by a-vector 23266 33 25 method 0.00 eV. 23266 33 26 ERR-ANALYS Uncertainty is not given. 23266 33 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 33 28 (COREL,23266032) Average data 23266 33 29 ENDBIB 27 0 23266 33 30 COMMON 1 3 23266 33 31 EN 23266 33 32 EV 23266 33 33 0.0253 23266 33 34 ENDCOMMON 3 0 23266 33 35 DATA 2 3 23266 33 36 DATA DECAY-FLAG 23266 33 37 B NO-DIM 23266 33 38 13.14 1. 23266 33 39 12.93 2. 23266 33 40 13.04 3. 23266 33 41 ENDDATA 5 0 23266 33 42 ENDSUBENT 41 0 23266 3399999 SUBENT 23266034 20230215 231423266 34 1 BIB 9 33 23266 34 2 REACTION 1((26-FE-58(N,G)26-FE-59,,RI,,AV)// 23266 34 3 (26-FE-58(N,G)26-FE-59,,SIG,,AV)) 23266 34 4 2((26-FE-58(N,G)26-FE-59,,RI)// 23266 34 5 (26-FE-58(N,G)26-FE-59,,SIG)) 23266 34 6 Q0 value (ratio of resonance integral to thermal 23266 34 7 neutron activation cross-section) 23266 34 8 SAMPLE - Provider - IRMM 23266 34 9 Matrix - Wire,Al alloy 23266 34 10 Elemental content, % weight - 0.2 23266 34 11 Average sample thickness, mm - 1. 23266 34 12 - Provider - Goodfellow 23266 34 13 Matrix - Foil 23266 34 14 -Elemental content, % weight - 99.99 23266 34 15 Average sample thickness, mm - 0.5 23266 34 16 -Elemental content, % weight - >99.99 23266 34 17 Average sample thickness, mm - 0.25 23266 34 18 (26-FE-58,NAT=0.00282) 0.282+-0.004 % 23266 34 19 METHOD Measurement at channels S84, Y4, X26. 23266 34 20 DECAY-DATA (26-FE-59,44.5D,DG,142.7,0.0102,DG,192.3,0.0308, 23266 34 21 DG,1099.3,0.5650,DG,1291.6,0.4320) 23266 34 22 ANALYSIS The Q0 factor was determined by 23266 34 23 1- the classical method: through the weighted mean and 23266 34 24 observed standard deviation of the 3 irradiation 23266 34 25 channels employed (S84, X26), when inputting Er 23266 34 26 factors from the literature. 23266 34 27 2- the a-vector method: through the parameters 23266 34 28 (m, b) --> determination of the value as well. 23266 34 29 ADD-RES Effective resonance Energy was defined by a-vect23266 34 30 method to be 252.9 eV ( +-18%, 2sigma). 23266 34 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 34 32 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 34 33 1(DEP,23266035) Directly measured data . 23266 34 34 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 34 35 ENDBIB 33 0 23266 34 36 COMMON 2 3 23266 34 37 EN-MIN-NM EN-DN 23266 34 38 EV EV 23266 34 39 0.55 0.0253 23266 34 40 ENDCOMMON 3 0 23266 34 41 DATA 4 1 23266 34 42 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 34 43 NO-DIM PER-CENT NO-DIM PER-CENT 23266 34 44 0.99 2. 0.97 1.5 23266 34 45 ENDDATA 3 0 23266 34 46 ENDSUBENT 45 0 23266 3499999 SUBENT 23266035 20141210 224123266 35 1 BIB 7 36 23266 35 2 REACTION ((26-FE-58(N,G)26-FE-59,,RI)// 23266 35 3 (26-FE-58(N,G)26-FE-59,,SIG)) 23266 35 4 Q0 value (ratio of resonance integral to thermal 23266 35 5 neutron activation cross-section) 23266 35 6 SAMPLE - Provider - IRMM 23266 35 7 Matrix - Wire,Al alloy 23266 35 8 Elemental content, % weight - 0.2 23266 35 9 Average sample thickness, mm - 1. 23266 35 10 - Provider - Goodfellow 23266 35 11 Matrix - Foil 23266 35 12 -Elemental content, % weight - 99.99 23266 35 13 Average sample thickness, mm - 0.5 23266 35 14 -Elemental content, % weight - >99.99 23266 35 15 Average sample thickness, mm - 0.25 23266 35 16 (26-FE-58,NAT=0.00282) 0.282+-0.004 % 23266 35 17 DECAY-DATA (26-FE-59,44.5D,DG,142.7,0.0102,DG,192.3,0.0308, 23266 35 18 DG,1099.3,0.5650,DG,1291.6,0.4320) 23266 35 19 FLAG Measurement at channels: 23266 35 20 (1.) S84, 23266 35 21 (2.) Y4, 23266 35 22 (3.) X26 . 23266 35 23 ANALYSIS The Q0 factor was determined by the classical method 23266 35 24 when inputting effective resonance energy factors 23266 35 25 from the literature. 23266 35 26 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 35 27 uncertainties ( 1 sigma) from: 23266 35 28 (ERR-1) alpha factor, 23266 35 29 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 35 30 epithermal flux for gold, 23266 35 31 (ERR-3) effective resonance energy Er, 23266 35 32 (ERR-4) Cd transmission factor FCd 23266 35 33 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 35 34 bare and Cd-covered sample. 23266 35 35 (ERR-S) Standard deviation. 23266 35 36 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 35 37 (COREL,23266034) Average data . 23266 35 38 ENDBIB 36 0 23266 35 39 COMMON 2 3 23266 35 40 EN-MIN-NM EN-DN 23266 35 41 EV EV 23266 35 42 0.55 0.0253 23266 35 43 ENDCOMMON 3 0 23266 35 44 DATA 9 3 23266 35 45 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 35 46 ERR-5 ERR-SYS FLAG 23266 35 47 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 35 48 PER-CENT PER-CENT NO-DIM 23266 35 49 0.96 0.5 1.05 1.1 0.1 0.55 23266 35 50 0.65 1.75 1. 23266 35 51 1.00 0.25 0.65 1.25 0.15 0.55 23266 35 52 0.65 1.75 2. 23266 35 53 1.01 0.5 2.05 1.6 0.25 0.6 23266 35 54 0.7 2.75 3. 23266 35 55 ENDDATA 10 0 23266 35 56 ENDSUBENT 55 0 23266 3599999 SUBENT 23266036 20230215 231423266 36 1 BIB 5 11 23266 36 2 REACTION (26-FE-58(N,G)26-FE-59,,SIG,,AV) 23266 36 3 SIG-0 - the average thermal neutron cross-section . 23266 36 4 for neutrons at an average energy of E0=25.3 meV 23266 36 5 or velocity v0=2200 m/s. 23266 36 6 ANALYSIS Derived from directly measured data. 23266 36 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 36 8 Uncertainty on exp. SIG-0 value comes from to the 23266 36 9 observed SD between gamma-lines. 23266 36 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 36 11 (DEP,23266037) Directly measured data. 23266 36 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 36 13 ENDBIB 11 0 23266 36 14 COMMON 1 3 23266 36 15 EN 23266 36 16 EV 23266 36 17 0.0253 23266 36 18 ENDCOMMON 3 0 23266 36 19 DATA 2 1 23266 36 20 DATA DATA-ERR 23266 36 21 B B 23266 36 22 1.30 0.01 23266 36 23 ENDDATA 3 0 23266 36 24 ENDSUBENT 23 0 23266 3699999 SUBENT 23266037 20141210 224123266 37 1 BIB 9 37 23266 37 2 REACTION (26-FE-58(N,G)26-FE-59,,SIG) 23266 37 3 Directly measured thermal neutron cross-section SIG-0 23266 37 4 SAMPLE - Provider - IRMM 23266 37 5 Matrix - Wire,Al alloy 23266 37 6 Elemental content, % weight - 0.2 23266 37 7 Average sample thickness, mm - 1. 23266 37 8 - Provider - Goodfellow 23266 37 9 Matrix - Foil 23266 37 10 -Elemental content, % weight - 99.99 23266 37 11 Average sample thickness, mm - 0.5 23266 37 12 -Elemental content, % weight - >99.99 23266 37 13 Average sample thickness, mm - 0.25 23266 37 14 (26-FE-58,NAT=0.00282) 0.282+-0.004 % 23266 37 15 DECAY-DATA ((1.)26-FE-59,44.5D,DG,142.7,0.0102) 23266 37 16 ((2.)26-FE-59,44.5D,DG,192.3,0.03080) 23266 37 17 ((3.)26-FE-59,44.5D,DG,1099.3,0.5650) reference line 23266 37 18 ((4.)26-FE-59,44.5D,DG,1291.6,0.4320) 23266 37 19 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 37 20 FLAG (5.) C-s measured by 142.7 and 192.3 keV gamma 23266 37 21 line are 1.24 and 1.19 b, they were not used in 23266 37 22 averaging. 23266 37 23 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 37 24 extrapolated with aid of the k0-definition, atomic 23266 37 25 weight, isotopic composition, the gamma intensities 23266 37 26 values. 23266 37 27 Defined according to their ADS(activation decay scheme,23266 37 28 including decay branching factors). 23266 37 29 ADD-RES Measured k0-values with one-sigma uncertainty 23266 37 30 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 37 31 846.8 4.94E-1 (+-0.7%) 23266 37 32 1810.7 1.32E-1 (+-0.4%) 23266 37 33 2113.1 7.04E-2 (+-0.2%) 23266 37 34 Effective resonance energy defined by a-vector 23266 37 35 method 0.00 eV. 23266 37 36 ERR-ANALYS Uncertainty is not given. 23266 37 37 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 37 38 (COREL,23266036) Average data 23266 37 39 ENDBIB 37 0 23266 37 40 COMMON 1 3 23266 37 41 EN 23266 37 42 EV 23266 37 43 0.0253 23266 37 44 ENDCOMMON 3 0 23266 37 45 DATA 3 4 23266 37 46 DATA DECAY-FLAG FLAG 23266 37 47 B NO-DIM NO-DIM 23266 37 48 1.24 1. 5. 23266 37 49 1.19 2. 5. 23266 37 50 1.30 3. 23266 37 51 1.29 4. 23266 37 52 ENDDATA 6 0 23266 37 53 ENDSUBENT 52 0 23266 3799999 SUBENT 23266038 20230215 231423266 38 1 BIB 8 24 23266 38 2 REACTION ((27-CO-59(N,G)27-CO-60-M,,RI,,AV)// 23266 38 3 (27-CO-59(N,G)27-CO-60-M,,SIG,,AV)) 23266 38 4 Q0 value (ratio of resonance integral to thermal 23266 38 5 neutron activation cross-section) 23266 38 6 SAMPLE - Provider - IRMM 23266 38 7 Matrix - Foil,Al alloy 23266 38 8 Elemental content, % weight - 1. 23266 38 9 Average sample thickness, mm - 0.1 23266 38 10 (27-CO-59,NAT=1.00) 100.% 23266 38 11 METHOD Measurement at channels S84. 23266 38 12 DECAY-DATA (27-CO-60-M,10.47MIN,DG,58.6,0.02036,DG,1332.5,0.00240)23266 38 13 10.47+-0.01 MIN 23266 38 14 (27-CO-60-G,5.271YR,DG,1173.2,0.99850, 23266 38 15 DG,1332.5,0.99983) 23266 38 16 5.371+-0.008 yr 23266 38 17 ANALYSIS The Q0 factor was determined by 23266 38 18 - the classical method: through the weighted mean and 23266 38 19 observed standard deviation of the 3 irradiation 23266 38 20 channels employed (S84, X26), when inputting Er 23266 38 21 factors from the literature. 23266 38 22 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 38 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 38 24 1(DEP,23266039) Directly measured data . 23266 38 25 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 38 26 ENDBIB 24 0 23266 38 27 COMMON 2 3 23266 38 28 EN-MIN-NM EN-DN 23266 38 29 EV EV 23266 38 30 0.55 0.0253 23266 38 31 ENDCOMMON 3 0 23266 38 32 DATA 2 1 23266 38 33 DATA DATA-ERR 23266 38 34 NO-DIM PER-CENT 23266 38 35 1.97 1.5 23266 38 36 ENDDATA 3 0 23266 38 37 ENDSUBENT 36 0 23266 3899999 SUBENT 23266039 20141210 224123266 39 1 BIB 7 30 23266 39 2 REACTION ((27-CO-59(N,G)27-CO-60-M,,RI)// 23266 39 3 (27-CO-59(N,G)27-CO-60-M,,SIG)) 23266 39 4 Q0 value (ratio of resonance integral to thermal 23266 39 5 neutron activation cross-section) 23266 39 6 SAMPLE - Provider - IRMM 23266 39 7 Matrix - Foil,Al alloy 23266 39 8 Elemental content, % weight - 1. 23266 39 9 Average sample thickness, mm - 0.1 23266 39 10 (27-CO-59,NAT=1.00) 100.% 23266 39 11 DECAY-DATA (27-CO-60-M,10.47MIN,DG,58.6,0.02036,DG,1332.5,0.00240)23266 39 12 10.47+-0.01 MIN 23266 39 13 (27-CO-60-G,5.271YR,DG,1173.2,0.99850, 23266 39 14 DG,1332.5,0.99983) 23266 39 15 5.371+-0.008 yr 23266 39 16 METHOD Measurement at channels S84. 23266 39 17 ANALYSIS The Q0 factor was determined by the classical method 23266 39 18 when inputting effective resonance energy factors 23266 39 19 from the literature. 23266 39 20 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 39 21 uncertainties ( 1 sigma) from: 23266 39 22 (ERR-1) alpha factor, 23266 39 23 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 39 24 epithermal flux for gold, 23266 39 25 (ERR-3) effective resonance energy Er, 23266 39 26 (ERR-4) Cd transmission factor FCd 23266 39 27 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 39 28 bare and Cd-covered sample. 23266 39 29 (ERR-S) Standard deviation. 23266 39 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 39 31 (COREL,23266038) Average data . 23266 39 32 ENDBIB 30 0 23266 39 33 COMMON 2 3 23266 39 34 EN-MIN-NM EN-DN 23266 39 35 EV EV 23266 39 36 0.55 0.0253 23266 39 37 ENDCOMMON 3 0 23266 39 38 DATA 8 1 23266 39 39 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 39 40 ERR-5 ERR-SYS 23266 39 41 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 39 42 PER-CENT PER-CENT 23266 39 43 1.97 1.5 0.85 1.4 0.1 0.55 23266 39 44 0.65 1.85 23266 39 45 ENDDATA 6 0 23266 39 46 ENDSUBENT 45 0 23266 3999999 SUBENT 23266040 20230215 231423266 40 1 BIB 6 12 23266 40 2 REACTION (27-CO-59(N,G)27-CO-60-M,,SIG,,AV) 23266 40 3 SIG-0 - the average thermal neutron cross-section . 23266 40 4 for neutrons at an average energy of E0=25.3 meV 23266 40 5 or velocity v0=2200 m/s. 23266 40 6 DECAY-DATA (27-CO-60-M,10.47MIN) 23266 40 7 ANALYSIS Derived from directly measured data. 23266 40 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 40 9 Uncertainty on exp. SIG-0 value comes from to the 23266 40 10 observed SD between gamma-lines. 23266 40 11 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 40 12 (DEP,23266041) Directly measured data. 23266 40 13 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 40 14 ENDBIB 12 0 23266 40 15 COMMON 1 3 23266 40 16 EN 23266 40 17 EV 23266 40 18 0.0253 23266 40 19 ENDCOMMON 3 0 23266 40 20 DATA 2 1 23266 40 21 DATA DATA-ERR 23266 40 22 B B 23266 40 23 20.7 0.5 23266 40 24 ENDDATA 3 0 23266 40 25 ENDSUBENT 24 0 23266 4099999 SUBENT 23266041 20141210 224123266 41 1 BIB 8 27 23266 41 2 REACTION (27-CO-59(N,G)27-CO-60-M,,SIG) 23266 41 3 Directly measured thermal neutron cross-section SIG-0 23266 41 4 SAMPLE - Provider - IRMM 23266 41 5 Matrix - Foil,Al alloy 23266 41 6 Elemental content, % weight - 1. 23266 41 7 Average sample thickness, mm - 0.1 23266 41 8 (27-CO-59,NAT=1.00) 100.% 23266 41 9 DECAY-DATA ((1.)27-CO-60-M,10.47MIN,DG,58.6,0.02036) 23266 41 10 ((2.)27-CO-60-M,10.47MIN,DG,1332.5,0.00240) 23266 41 11 10.47+-0.01 MIN 23266 41 12 (27-CO-60-G,5.271YR,DG,1173.2,0.99850, 23266 41 13 DG,1332.5,0.99983) 23266 41 14 5.371+-0.008 yr 23266 41 15 METHOD Measurement at channel S84 . 23266 41 16 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 41 17 extrapolated with aid of the k0-definition, atomic 23266 41 18 weight, isotopic composition, the gamma intensities 23266 41 19 values. 23266 41 20 Defined according to their ADS(activation decay scheme,23266 41 21 including decay branching factors). 23266 41 22 ADD-RES Measured k0-values with one-sigma uncertainty 23266 41 23 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 41 24 58.6 1.47E-2 (+-1.2%) 23266 41 25 1332.5 1.79E-3 (+-1.4%) 23266 41 26 ERR-ANALYS Uncertainty is not given. 23266 41 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 41 28 (COREL,23266040) Average data 23266 41 29 ENDBIB 27 0 23266 41 30 COMMON 1 3 23266 41 31 EN 23266 41 32 EV 23266 41 33 0.0253 23266 41 34 ENDCOMMON 3 0 23266 41 35 DATA 2 2 23266 41 36 DATA DECAY-FLAG 23266 41 37 B NO-DIM 23266 41 38 20.4 1. 23266 41 39 21.0 2. 23266 41 40 ENDDATA 4 0 23266 41 41 ENDSUBENT 40 0 23266 4199999 SUBENT 23266042 20230215 231423266 42 1 BIB 9 29 23266 42 2 REACTION 1((27-CO-59(N,G)27-CO-60,,RI,,AV)// 23266 42 3 (27-CO-59(N,G)27-CO-60,,SIG,,AV)) 23266 42 4 2((27-CO-59(N,G)27-CO-60,,RI)// 23266 42 5 (27-CO-59(N,G)27-CO-60,,SIG)) M+G 23266 42 6 Q0 value (ratio of resonance integral to thermal 23266 42 7 neutron activation cross-section) 23266 42 8 SAMPLE - Provider - IRMM 23266 42 9 Matrix - Foil,Al alloy 23266 42 10 Elemental content, % weight - 1. 23266 42 11 Average sample thickness, mm - 0.1 23266 42 12 (27-CO-59,NAT=1.00) 100.% 23266 42 13 METHOD Measurement at channel S84. 23266 42 14 DECAY-DATA (27-CO-60-M,10.47MIN,DG,1332.5,0.00240) 23266 42 15 10.47+-0.01 MIN 23266 42 16 (27-CO-60-G,5.271YR,DG,1332.5,0.99983) 23266 42 17 5.271+-0.008 yr 23266 42 18 ANALYSIS The Q0 factor was determined by 23266 42 19 1- the classical method: through the weighted mean and 23266 42 20 observed standard deviation of the 3 irradiation 23266 42 21 channels employed (S84, X26), when inputting Er 23266 42 22 factors from the literature. 23266 42 23 2- the a-vector method: through the parameters 23266 42 24 (m, b) --> determination of the value as well. 23266 42 25 ADD-RES Effective resonance Energy was defined by a-vect23266 42 26 method to be 109. eV ( +-8%, 2sigma). 23266 42 27 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 42 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 42 29 1(DEP,23266043) Directly measured data . 23266 42 30 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 42 31 ENDBIB 29 0 23266 42 32 COMMON 2 3 23266 42 33 EN-MIN-NM EN-DN 23266 42 34 EV EV 23266 42 35 0.55 0.0253 23266 42 36 ENDCOMMON 3 0 23266 42 37 DATA 4 1 23266 42 38 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 42 39 NO-DIM PER-CENT NO-DIM PER-CENT 23266 42 40 1.99 1. 1.96 2. 23266 42 41 ENDDATA 3 0 23266 42 42 ENDSUBENT 41 0 23266 4299999 SUBENT 23266043 20141210 224123266 43 1 BIB 7 32 23266 43 2 REACTION ((27-CO-59(N,G)27-CO-60,,RI)// 23266 43 3 (27-CO-59(N,G)27-CO-60,,SIG)) M+G 23266 43 4 Q0 value (ratio of resonance integral to thermal 23266 43 5 neutron activation cross-section) 23266 43 6 SAMPLE - Provider - IRMM 23266 43 7 Matrix - Foil,Al alloy 23266 43 8 Elemental content, % weight - 1. 23266 43 9 Average sample thickness, mm - 0.1 23266 43 10 (27-CO-59,NAT=1.00) 100.% 23266 43 11 DECAY-DATA (27-CO-60-M,10.47MIN,DG,1332.5,0.00240) 23266 43 12 10.47+-0.01 MIN 23266 43 13 (27-CO-60-G,5.271YR,DG,1332.5,0.99983) 23266 43 14 5.371+-0.008 yr 23266 43 15 FLAG Measurement at channels 23266 43 16 (1.) S84, 23266 43 17 (2.) Y4 23266 43 18 (3.) X26 23266 43 19 ANALYSIS The Q0 factor was determined by the classical method 23266 43 20 when inputting effective resonance energy factors 23266 43 21 from the literature. 23266 43 22 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 43 23 uncertainties ( 1 sigma) from: 23266 43 24 (ERR-1) alpha factor, 23266 43 25 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 43 26 epithermal flux for gold, 23266 43 27 (ERR-3) effective resonance energy Er, 23266 43 28 (ERR-4) Cd transmission factor FCd 23266 43 29 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 43 30 bare and Cd-covered sample. 23266 43 31 (ERR-S) Standard deviation. 23266 43 32 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 43 33 (COREL,23266042) Average data . 23266 43 34 ENDBIB 32 0 23266 43 35 COMMON 2 3 23266 43 36 EN-MIN-NM EN-DN 23266 43 37 EV EV 23266 43 38 0.55 0.0253 23266 43 39 ENDCOMMON 3 0 23266 43 40 DATA 9 3 23266 43 41 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 43 42 ERR-5 ERR-SYS FLAG 23266 43 43 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 43 44 PER-CENT PER-CENT NO-DIM 23266 43 45 1.96 0.25 0.85 1.4 0.1 0.55 23266 43 46 0.65 1.85 1. 23266 43 47 2.01 0.25 0.5 1.2 0.1 0.55 23266 43 48 0.65 1.55 2. 23266 43 49 1.99 0.25 1.05 1.85 0.15 0.6 23266 43 50 0.65 2.3 3. 23266 43 51 ENDDATA 10 0 23266 43 52 ENDSUBENT 51 0 23266 4399999 SUBENT 23266044 20230215 231423266 44 1 BIB 5 11 23266 44 2 REACTION (27-CO-59(N,G)27-CO-60,,SIG,,AV) M+G 23266 44 3 SIG-0 - the average thermal neutron cross-section . 23266 44 4 for neutrons at an average energy of E0=25.3 meV 23266 44 5 or velocity v0=2200 m/s. 23266 44 6 ANALYSIS Derived from directly measured data. 23266 44 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 44 8 Uncertainty on exp. SIG-0 value comes from to the 23266 44 9 observed SD between gamma-lines. 23266 44 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 44 11 (DEP,23266045) Directly measured data. 23266 44 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 44 13 ENDBIB 11 0 23266 44 14 COMMON 1 3 23266 44 15 EN 23266 44 16 EV 23266 44 17 0.0253 23266 44 18 ENDCOMMON 3 0 23266 44 19 DATA 2 1 23266 44 20 DATA DATA-ERR 23266 44 21 B B 23266 44 22 37.15 0.2 23266 44 23 ENDDATA 3 0 23266 44 24 ENDSUBENT 23 0 23266 4499999 SUBENT 23266045 20141210 224123266 45 1 BIB 8 27 23266 45 2 REACTION (27-CO-59(N,G)27-CO-60,,SIG) M+G 23266 45 3 Directly measured thermal neutron cross-section SIG-0 23266 45 4 SAMPLE - Provider - IRMM 23266 45 5 Matrix - Foil,Al alloy 23266 45 6 Elemental content, % weight - 1. 23266 45 7 Average sample thickness, mm - 0.1 23266 45 8 (27-CO-59,NAT=1.00) 100.% 23266 45 9 DECAY-DATA (27-CO-60-M,10.47MIN,DG,58.6,0.2036) 23266 45 10 (27-CO-60-M,10.47MIN,DG,1332.5,0.00240) 23266 45 11 10.47+-0.01 min 23266 45 12 ((1.)27-CO-60-G,5.271YR,DG,1173.2,0.99850) 23266 45 13 ((2.)27-CO-60-G,5.271YR,DG,1332.5,0.99983) 23266 45 14 5.371+-0.008 yr 23266 45 15 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 45 16 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 45 17 extrapolated with aid of the k0-definition, atomic 23266 45 18 weight, isotopic composition, the gamma intensities 23266 45 19 values. 23266 45 20 Defined according to their ADS(activation decay scheme,23266 45 21 including decay branching factors). 23266 45 22 ADD-RES Measured k0-values with one-sigma uncertainty 23266 45 23 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 45 24 1173.2 1.32E+0 (+-0.4%) 23266 45 25 1332.5 1.32E+0 (+-0.4%) 23266 45 26 ERR-ANALYS Uncertainty is not given. 23266 45 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 45 28 (COREL,23266044) Average data 23266 45 29 ENDBIB 27 0 23266 45 30 COMMON 1 3 23266 45 31 EN 23266 45 32 EV 23266 45 33 0.0253 23266 45 34 ENDCOMMON 3 0 23266 45 35 DATA 2 2 23266 45 36 DATA DECAY-FLAG 23266 45 37 B NO-DIM 23266 45 38 37.16 1. 23266 45 39 37.14 2. 23266 45 40 ENDDATA 4 0 23266 45 41 ENDSUBENT 40 0 23266 4599999 SUBENT 23266046 20230215 231423266 46 1 BIB 5 11 23266 46 2 REACTION (27-CO-59(N,G)27-CO-60-G,,SIG,,AV) 23266 46 3 SIG-0 - the average thermal neutron cross-section . 23266 46 4 for neutrons at an average energy of E0=25.3 meV 23266 46 5 or velocity v0=2200 m/s. 23266 46 6 ANALYSIS Derived from directly measured data. 23266 46 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 46 8 Uncertainty on exp. SIG-0 value comes from to the 23266 46 9 observed SD between gamma-lines. 23266 46 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 46 11 (DEP,23266047) Directly measured data. 23266 46 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 46 13 ENDBIB 11 0 23266 46 14 COMMON 1 3 23266 46 15 EN 23266 46 16 EV 23266 46 17 0.0253 23266 46 18 ENDCOMMON 3 0 23266 46 19 DATA 2 1 23266 46 20 DATA DATA-ERR 23266 46 21 B B 23266 46 22 16.70 0.17 23266 46 23 ENDDATA 3 0 23266 46 24 ENDSUBENT 23 0 23266 4699999 SUBENT 23266047 20141210 224123266 47 1 BIB 8 24 23266 47 2 REACTION (27-CO-59(N,G)27-CO-60-G,,SIG) 23266 47 3 Directly measured thermal neutron cross-section SIG-0 23266 47 4 SAMPLE - Provider - IRMM 23266 47 5 Matrix - Foil,Al alloy 23266 47 6 Elemental content, % weight - 1. 23266 47 7 Average sample thickness, mm - 0.1 23266 47 8 (27-CO-59,NAT=1.00) 100.% 23266 47 9 DECAY-DATA (27-CO-60-M,10.47MIN,DG,1332.5,0.00240) 23266 47 10 10.47+-0.01 min 23266 47 11 (27-CO-60-G,5.271YR,DG,1332.5,0.99983) 23266 47 12 5.371+-0.008 yr 23266 47 13 METHOD Measurement at channel S84 . 23266 47 14 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 47 15 extrapolated with aid of the k0-definition, atomic 23266 47 16 weight, isotopic composition, the gamma intensities 23266 47 17 values. 23266 47 18 Defined according to their ADS(activation decay scheme,23266 47 19 including decay branching factors). 23266 47 20 ADD-RES Measured k0-values with one-sigma uncertainty 23266 47 21 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 47 22 1332.5 5.92E-1 (+-0.4%) 23266 47 23 ERR-ANALYS Uncertainty is not given. 23266 47 24 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 47 25 (COREL,23266046) Average data 23266 47 26 ENDBIB 24 0 23266 47 27 COMMON 1 3 23266 47 28 EN 23266 47 29 EV 23266 47 30 0.0253 23266 47 31 ENDCOMMON 3 0 23266 47 32 DATA 1 1 23266 47 33 DATA 23266 47 34 B 23266 47 35 16.7 23266 47 36 ENDDATA 3 0 23266 47 37 ENDSUBENT 36 0 23266 4799999 SUBENT 23266048 20230215 231423266 48 1 BIB 8 18 23266 48 2 REACTION ((28-NI-64(N,G)28-NI-65,,RI,,AV)// 23266 48 3 (28-NI-64(N,G)28-NI-65,,SIG,,AV)) 23266 48 4 Q0 value (ratio of resonance integral to thermal 23266 48 5 neutron activation cross-section) 23266 48 6 SAMPLE - Provider - CBNM 23266 48 7 Matrix - Foil 23266 48 8 Elemental content, % weight - >99.99 23266 48 9 Average sample thickness, mm - 0.1 23266 48 10 (28-NI-65,NAT=0.009255) 0.9255+-0.0019 % 23266 48 11 METHOD Measurement at channel S84. 23266 48 12 DECAY-DATA (28-NI-65,2.517HR,DG,366.3,0.0481,DG,1115.5,0.1543, 23266 48 13 DG,1481.8,0.2359) 23266 48 14 ANALYSIS The Q0 factor was determined by 23266 48 15 - the classical method. 23266 48 16 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 48 17 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 48 18 (DEP,23266049) Directly measured data . 23266 48 19 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 48 20 ENDBIB 18 0 23266 48 21 COMMON 2 3 23266 48 22 EN-MIN-NM EN-DN 23266 48 23 EV EV 23266 48 24 0.55 0.0253 23266 48 25 ENDCOMMON 3 0 23266 48 26 DATA 2 1 23266 48 27 DATA DATA-ERR 23266 48 28 NO-DIM PER-CENT 23266 48 29 0.46 1.5 23266 48 30 ENDDATA 3 0 23266 48 31 ENDSUBENT 30 0 23266 4899999 SUBENT 23266049 20141210 224123266 49 1 BIB 7 27 23266 49 2 REACTION ((28-NI-64(N,G)28-NI-65,,RI)// 23266 49 3 (28-NI-64(N,G)28-NI-65,,SIG)) M+G 23266 49 4 Q0 value (ratio of resonance integral to thermal 23266 49 5 neutron activation cross-section) 23266 49 6 SAMPLE - Provider - CBNM 23266 49 7 Matrix - Foil 23266 49 8 Elemental content, % weight - >99.99 23266 49 9 Average sample thickness, mm - 0.1 23266 49 10 (28-NI-65,NAT=0.009255) 0.9255+-0.0019 % 23266 49 11 METHOD Measurement at channels S84. 23266 49 12 DECAY-DATA (28-NI-65,2.517HR,DG,366.3,0.0481,DG,1115.5,0.1543, 23266 49 13 DG,1481.8,0.2359) 23266 49 14 ANALYSIS The Q0 factor was determined by the classical method 23266 49 15 when inputting effective resonance energy factors 23266 49 16 from the literature. 23266 49 17 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 49 18 uncertainties ( 1 sigma) from: 23266 49 19 (ERR-1) alpha factor, 23266 49 20 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 49 21 epithermal flux for gold, 23266 49 22 (ERR-3) effective resonance energy Er, 23266 49 23 (ERR-4) Cd transmission factor FCd 23266 49 24 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 49 25 bare and Cd-covered sample. 23266 49 26 (ERR-S) Standard deviation. 23266 49 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 49 28 (COREL,23266048) Average data . 23266 49 29 ENDBIB 27 0 23266 49 30 COMMON 2 3 23266 49 31 EN-MIN-NM EN-DN 23266 49 32 EV EV 23266 49 33 0.55 0.0253 23266 49 34 ENDCOMMON 3 0 23266 49 35 DATA 8 1 23266 49 36 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 49 37 ERR-5 ERR-SYS 23266 49 38 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 49 39 PER-CENT PER-CENT 23266 49 40 0.46 0.5 1.05 1.0 0.1 0.5 23266 49 41 0.55 1.65 23266 49 42 ENDDATA 6 0 23266 49 43 ENDSUBENT 42 0 23266 4999999 SUBENT 23266050 20230215 231423266 50 1 BIB 5 11 23266 50 2 REACTION (28-NI-64(N,G)28-NI-65,,SIG,,AV) 23266 50 3 SIG-0 - the average thermal neutron cross-section . 23266 50 4 for neutrons at an average energy of E0=25.3 meV 23266 50 5 or velocity v0=2200 m/s. 23266 50 6 ANALYSIS Derived from directly measured data. 23266 50 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 50 8 Uncertainty on exp. SIG-0 value comes from to the 23266 50 9 observed SD between gamma-lines. 23266 50 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 50 11 (DEP,23266051) Directly measured data. 23266 50 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 50 13 ENDBIB 11 0 23266 50 14 COMMON 1 3 23266 50 15 EN 23266 50 16 EV 23266 50 17 0.0253 23266 50 18 ENDCOMMON 3 0 23266 50 19 DATA 2 1 23266 50 20 DATA DATA-ERR 23266 50 21 B B 23266 50 22 1.62 0.01 23266 50 23 ENDDATA 3 0 23266 50 24 ENDSUBENT 23 0 23266 5099999 SUBENT 23266051 20141210 224123266 51 1 BIB 8 25 23266 51 2 REACTION (28-NI-64(N,G)28-NI-65,,SIG) 23266 51 3 Directly measured thermal neutron cross-section SIG-0 23266 51 4 SAMPLE - Provider - CBNM 23266 51 5 Matrix - Foil 23266 51 6 Elemental content, % weight - >99.99 23266 51 7 Average sample thickness, mm - 0.1 23266 51 8 (28-NI-65,NAT=0.009255) 0.9255+-0.0019 % 23266 51 9 DECAY-DATA ((1.)28-NI-65,2.517HR,DG,366.3,0.0481) 23266 51 10 ((2.)28-NI-65,2.517HR,DG,1115.5,0.1543) 23266 51 11 ((3.)28-NI-65,2.517HR,DG,1481.8,0.2359) reference line 23266 51 12 METHOD Measurement at channel S84 . 23266 51 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 51 14 extrapolated with aid of the k0-definition, atomic 23266 51 15 weight, isotopic composition, the gamma intensities 23266 51 16 values. 23266 51 17 Defined according to their ADS(activation decay scheme,23266 51 18 including decay branching factors). 23266 51 19 ADD-RES Measured k0-values with one-sigma uncertainty 23266 51 20 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 51 21 366.3 2.55E-5 (+-1.1%) 23266 51 22 1115.5 8.14E-5 (+-1.0%) 23266 51 23 1481.8 1.26E-4 (+-1.3%) 23266 51 24 ERR-ANALYS Uncertainty is not given. 23266 51 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 51 26 (COREL,23266050) Average data 23266 51 27 ENDBIB 25 0 23266 51 28 COMMON 1 3 23266 51 29 EN 23266 51 30 EV 23266 51 31 0.0253 23266 51 32 ENDCOMMON 3 0 23266 51 33 DATA 2 3 23266 51 34 DATA DECAY-FLAG 23266 51 35 B NO-DIM 23266 51 36 1.61 1. 23266 51 37 1.60 2. 23266 51 38 1.62 3. 23266 51 39 ENDDATA 5 0 23266 51 40 ENDSUBENT 39 0 23266 5199999 SUBENT 23266052 20230215 231423266 52 1 BIB 9 34 23266 52 2 REACTION 1((29-CU-63(N,G)29-CU-64,,RI,,AV)// 23266 52 3 (29-CU-63(N,G)29-CU-64,,SIG,,AV)) 23266 52 4 2((29-CU-63(N,G)29-CU-64,,RI)// 23266 52 5 (29-CU-63(N,G)29-CU-64,,SIG)) 23266 52 6 Q0 value (ratio of resonance integral to thermal 23266 52 7 neutron activation cross-section) 23266 52 8 SAMPLE - Provider - IRMM 23266 52 9 Matrix - Foil,Al alloy 23266 52 10 Elemental content, % weight - 10. 23266 52 11 Average sample thickness, mm - 0.1 23266 52 12 - Provider - Goodfellow 23266 52 13 Matrix - Wire 23266 52 14 Elemental content, % weight - 99.99 23266 52 15 Average sample thickness, mm - 1. 23266 52 16 - Provider - CBNM 23266 52 17 Matrix - Foil 23266 52 18 Elemental content, % weight - >99.99 23266 52 19 Average sample thickness, mm - 0.1 23266 52 20 (29-CU-63,NAT=0.6915) 69.15+-0.15 % 23266 52 21 METHOD Measurement at channels S84, Y4, X26 . 23266 52 22 DECAY-DATA (29-CU-64,12.70HR,DG,511.0,0.3500,DG,1345.8,0.00475) 23266 52 23 ANALYSIS The Q0 factor was determined by 23266 52 24 1- the classical method: through the weighted mean and 23266 52 25 observed standard deviation of the 3 irradiation 23266 52 26 channels employed (S84, X26), when inputting Er 23266 52 27 factors from the literature. 23266 52 28 2- the a-vector method: through the parameters 23266 52 29 (m, b) --> determination of the value as well. 23266 52 30 ADD-RES Effective resonance Energy was defined by a-vect23266 52 31 method to be 952.eV ( +-12%, 2sigma). 23266 52 32 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 52 33 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 52 34 1(DEP,23266053) Directly measured data . 23266 52 35 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 52 36 ENDBIB 34 0 23266 52 37 COMMON 2 3 23266 52 38 EN-MIN-NM EN-DN 23266 52 39 EV EV 23266 52 40 0.55 0.0253 23266 52 41 ENDCOMMON 3 0 23266 52 42 DATA 4 1 23266 52 43 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 52 44 NO-DIM PER-CENT NO-DIM PER-CENT 23266 52 45 1.11 2.5 1.10 1.5 23266 52 46 ENDDATA 3 0 23266 52 47 ENDSUBENT 46 0 23266 5299999 SUBENT 23266053 20180202 226823266 53 1 BIB 8 39 23266 53 2 REACTION ((29-CU-63(N,G)29-CU-64,,RI)// 23266 53 3 (29-CU-63(N,G)29-CU-64,,SIG)) 23266 53 4 Q0 value (ratio of resonance integral to thermal 23266 53 5 neutron activation cross-section) 23266 53 6 SAMPLE - Provider - IRMM 23266 53 7 Matrix - Foil,Al alloy 23266 53 8 Elemental content, % weight - 10. 23266 53 9 Average sample thickness, mm - 0.1 23266 53 10 - Provider - Goodfellow 23266 53 11 Matrix - Wire 23266 53 12 Elemental content, % weight - 99.99 23266 53 13 Average sample thickness, mm - 1. 23266 53 14 - Provider - CBNM 23266 53 15 Matrix - Foil 23266 53 16 Elemental content, % weight - >99.99 23266 53 17 Average sample thickness, mm - 0.1 23266 53 18 (29-CU-63,NAT=0.6915) 69.15+-0.15 % 23266 53 19 DECAY-DATA (29-CU-64,12.70HR,DG,511.0,0.3500, 23266 53 20 DG,1345.8,0.00475) 23266 53 21 FLAG Measurement at channels 23266 53 22 (1.) S84, 23266 53 23 (2.) Y4 23266 53 24 (3.) X26 23266 53 25 ANALYSIS The Q0 factor was determined by the classical method 23266 53 26 when inputting effective resonance energy factors 23266 53 27 from the literature. 23266 53 28 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 53 29 uncertainties ( 1 sigma) from: 23266 53 30 (ERR-1) alpha factor, 23266 53 31 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 53 32 epithermal flux for gold, 23266 53 33 (ERR-3) effective resonance energy Er, 23266 53 34 (ERR-4) Cd transmission factor FCd 23266 53 35 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 53 36 bare and Cd-covered sample. 23266 53 37 (ERR-S) Standard deviation. 23266 53 38 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 53 39 (COREL,23266052) Average data . 23266 53 40 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 53 41 ENDBIB 39 0 23266 53 42 COMMON 2 3 23266 53 43 EN-MIN-NM EN-DN 23266 53 44 EV EV 23266 53 45 0.55 0.0253 23266 53 46 ENDCOMMON 3 0 23266 53 47 DATA 9 3 23266 53 48 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 53 49 ERR-5 ERR-SYS FLAG 23266 53 50 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 53 51 PER-CENT PER-CENT NO-DIM 23266 53 52 1.12 2.0 1.15 1.05 0.1 0.55 23266 53 53 0.6 1.75 1. 23266 53 54 1.08 1.5 0.7 1.3 0.1 0.55 23266 53 55 0.6 1.7 2. 23266 53 56 1.15 2.5 2.3 1.65 0.15 0.6 23266 53 57 0.7 3.0 3. 23266 53 58 ENDDATA 10 0 23266 53 59 ENDSUBENT 58 0 23266 5399999 SUBENT 23266054 20230215 231423266 54 1 BIB 5 12 23266 54 2 REACTION (29-CU-63(N,G)29-CU-64,,SIG,,AV) 23266 54 3 SIG-0 - the average thermal neutron cross-section . 23266 54 4 for neutrons at an average energy of E0=25.3 meV 23266 54 5 or velocity v0=2200 m/s. 23266 54 6 ANALYSIS Derived from directly measured data. 23266 54 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 54 8 Uncertainty on exp. SIG-0 value comes from to the 23266 54 9 observed standard deviation between gamma-lines. 23266 54 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 54 11 (DEP,23266055) Directly measured data. 23266 54 12 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 54 13 (20230215A) SD: SF8=AV added to REACTION codes. 23266 54 14 ENDBIB 12 0 23266 54 15 COMMON 1 3 23266 54 16 EN 23266 54 17 EV 23266 54 18 0.0253 23266 54 19 ENDCOMMON 3 0 23266 54 20 DATA 2 1 23266 54 21 DATA DATA-ERR 23266 54 22 B B 23266 54 23 4.52 0.02 23266 54 24 ENDDATA 3 0 23266 54 25 ENDSUBENT 24 0 23266 5499999 SUBENT 23266055 20141210 224123266 55 1 BIB 8 31 23266 55 2 REACTION (29-CU-63(N,G)29-CU-64,,SIG) 23266 55 3 Directly measured thermal neutron cross-section SIG-0 23266 55 4 SAMPLE - Provider - IRMM 23266 55 5 Matrix - Foil,Al alloy 23266 55 6 Elemental content, % weight - 10. 23266 55 7 Average sample thickness, mm - 0.1 23266 55 8 - Provider - Goodfellow 23266 55 9 Matrix - Wire 23266 55 10 Elemental content, % weight - 99.99 23266 55 11 Average sample thickness, mm - 1. 23266 55 12 - Provider - CBNM 23266 55 13 Matrix - Foil 23266 55 14 Elemental content, % weight - >99.99 23266 55 15 Average sample thickness, mm - 0.1 23266 55 16 (29-CU-63,NAT=0.6915) 69.15+-0.15 % 23266 55 17 DECAY-DATA ((1.)29-CU-64,12.70HR,DG,511.0,0.3500) reference line 23266 55 18 ((2.)29-CU-64,12.70HR,DG,1345.8,0.00475) 23266 55 19 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 55 20 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 55 21 extrapolated with aid of the k0-definition, atomic 23266 55 22 weight, isotopic composition, the gamma intensities 23266 55 23 values. 23266 55 24 Defined according to their ADS(activation decay scheme,23266 55 25 including decay branching factors). 23266 55 26 ADD-RES Measured k0-values with one-sigma uncertainty 23266 55 27 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 55 28 511.0 3.32E-2 (+-0.1%) 23266 55 29 1345.8 4.88E-4 (+-0.2%) 23266 55 30 ERR-ANALYS Uncertainty is not given. 23266 55 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 55 32 (COREL,23266054) Average data 23266 55 33 ENDBIB 31 0 23266 55 34 COMMON 1 3 23266 55 35 EN 23266 55 36 EV 23266 55 37 0.0253 23266 55 38 ENDCOMMON 3 0 23266 55 39 DATA 2 2 23266 55 40 DATA DECAY-FLAG 23266 55 41 B NO-DIM 23266 55 42 4.17 1. 23266 55 43 4.52 2. 23266 55 44 ENDDATA 4 0 23266 55 45 ENDSUBENT 44 0 23266 5599999 SUBENT 23266056 20230215 231423266 56 1 BIB 8 25 23266 56 2 REACTION ((29-CU-65(N,G)29-CU-66,,RI,,AV)// 23266 56 3 (29-CU-65(N,G)29-CU-66,,SIG,,AV)) 23266 56 4 Q0 value (ratio of resonance integral to thermal 23266 56 5 neutron activation cross-section) 23266 56 6 SAMPLE - Provider - IRMM 23266 56 7 Matrix - Foil,Al alloy 23266 56 8 Elemental content, % weight - 10. 23266 56 9 Average sample thickness, mm - 0.1 23266 56 10 - Provider - Goodfellow 23266 56 11 Matrix - Wire 23266 56 12 Elemental content, % weight - 99.99 23266 56 13 Average sample thickness, mm - 1. 23266 56 14 - Provider - CBNM 23266 56 15 Matrix - Foil 23266 56 16 Elemental content, % weight - >99.99 23266 56 17 Average sample thickness, mm - 0.1 23266 56 18 (29-CU-65,NAT=0.3085) 30.85+-0.15 % 23266 56 19 METHOD Measurement at channel S84. 23266 56 20 DECAY-DATA (29-CU-66,5.12MIN,DG,1039.2,0.0923) 23266 56 21 ANALYSIS The Q0 factor was determined by 23266 56 22 the classical method. 23266 56 23 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 56 24 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 56 25 (DEP,23266057) Directly measured data . 23266 56 26 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 56 27 ENDBIB 25 0 23266 56 28 COMMON 2 3 23266 56 29 EN-MIN-NM EN-DN 23266 56 30 EV EV 23266 56 31 0.55 0.0253 23266 56 32 ENDCOMMON 3 0 23266 56 33 DATA 2 1 23266 56 34 DATA DATA-ERR 23266 56 35 NO-DIM PER-CENT 23266 56 36 1.01 2. 23266 56 37 ENDDATA 3 0 23266 56 38 ENDSUBENT 37 0 23266 5699999 SUBENT 23266057 20141210 224123266 57 1 BIB 7 33 23266 57 2 REACTION ((29-CU-65(N,G)29-CU-66,,RI)// 23266 57 3 (29-CU-65(N,G)29-CU-66,,SIG)) 23266 57 4 Q0 value (ratio of resonance integral to thermal 23266 57 5 neutron activation cross-section) 23266 57 6 SAMPLE - Provider - IRMM 23266 57 7 Matrix - Foil,Al alloy 23266 57 8 Elemental content, % weight - 10. 23266 57 9 Average sample thickness, mm - 0.1 23266 57 10 - Provider - Goodfellow 23266 57 11 Matrix - Wire 23266 57 12 Elemental content, % weight - 99.99 23266 57 13 Average sample thickness, mm - 1. 23266 57 14 - Provider - CBNM 23266 57 15 Matrix - Foil 23266 57 16 Elemental content, % weight - >99.99 23266 57 17 Average sample thickness, mm - 0.1 23266 57 18 DECAY-DATA (29-CU-66,5.12MIN,DG,1039.2,0.0923) 23266 57 19 METHOD Measurement at channel S84 23266 57 20 ANALYSIS The Q0 factor was determined by the classical method 23266 57 21 when inputting effective resonance energy factors 23266 57 22 from the literature. 23266 57 23 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 57 24 uncertainties ( 1 sigma) from: 23266 57 25 (ERR-1) alpha factor, 23266 57 26 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 57 27 epithermal flux for gold, 23266 57 28 (ERR-3) effective resonance energy Er, 23266 57 29 (ERR-4) Cd transmission factor FCd, 23266 57 30 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 57 31 bare and Cd-covered sample. 23266 57 32 (ERR-S) Standard deviation. 23266 57 33 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 57 34 (COREL,23266056) Average data . 23266 57 35 ENDBIB 33 0 23266 57 36 COMMON 2 3 23266 57 37 EN-MIN-NM EN-DN 23266 57 38 EV EV 23266 57 39 0.55 0.0253 23266 57 40 ENDCOMMON 3 0 23266 57 41 DATA 8 1 23266 57 42 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 57 43 ERR-5 ERR-SYS 23266 57 44 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 57 45 PER-CENT PER-CENT 23266 57 46 1.01 0.5 1.15 1.05 0.1 0.5 23266 57 47 0.55 1.75 23266 57 48 ENDDATA 6 0 23266 57 49 ENDSUBENT 48 0 23266 5799999 SUBENT 23266058 20230215 231423266 58 1 BIB 5 11 23266 58 2 REACTION (29-CU-65(N,G)29-CU-66,,SIG,,AV) 23266 58 3 SIG-0 - the average thermal neutron cross-section . 23266 58 4 for neutrons at an average energy of E0=25.3 meV 23266 58 5 or velocity v0=2200 m/s. 23266 58 6 ANALYSIS Derived from directly measured data. 23266 58 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 58 8 Uncertainty on exp. SIG-0 value comes from to the 23266 58 9 observed SD between gamma-lines. 23266 58 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 58 11 (DEP,23266059) Directly measured data. 23266 58 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 58 13 ENDBIB 11 0 23266 58 14 COMMON 1 3 23266 58 15 EN 23266 58 16 EV 23266 58 17 0.0253 23266 58 18 ENDCOMMON 3 0 23266 58 19 DATA 2 1 23266 58 20 DATA DATA-ERR 23266 58 21 B B 23266 58 22 2.06 0.01 23266 58 23 ENDDATA 3 0 23266 58 24 ENDSUBENT 23 0 23266 5899999 SUBENT 23266059 20141210 224123266 59 1 BIB 8 29 23266 59 2 REACTION (29-CU-65(N,G)29-CU-66,,SIG) 23266 59 3 Directly measured thermal neutron cross-section SIG-0 23266 59 4 SAMPLE - Provider - IRMM 23266 59 5 Matrix - Foil,Al alloy 23266 59 6 Elemental content, % weight - 10. 23266 59 7 Average sample thickness, mm - 0.1 23266 59 8 - Provider - Goodfellow 23266 59 9 Matrix - Wire 23266 59 10 Elemental content, % weight - 99.99 23266 59 11 Average sample thickness, mm - 1. 23266 59 12 - Provider - CBNM 23266 59 13 Matrix - Foil 23266 59 14 Elemental content, % weight - >99.99 23266 59 15 Average sample thickness, mm - 0.1 23266 59 16 (29-CU-65,NAT=0.3085) 30.85+-0.15 % 23266 59 17 DECAY-DATA (29-CU-66,5.12MIN,DG,1039.2,0.0923) reference line 23266 59 18 METHOD Measurement at channel S84 . 23266 59 19 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 59 20 extrapolated with aid of the k0-definition, atomic 23266 59 21 weight, isotopic composition, the gamma intensities 23266 59 22 values. 23266 59 23 Defined according to their ADS(activation decay scheme,23266 59 24 including decay branching factors). 23266 59 25 ADD-RES Measured k0-values with one-sigma uncertainty 23266 59 26 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 59 27 1039.2 1.93E-3 (+-1.0%) 23266 59 28 ERR-ANALYS Uncertainty is not given. 23266 59 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 59 30 (COREL,23266058) Average data 23266 59 31 ENDBIB 29 0 23266 59 32 COMMON 1 3 23266 59 33 EN 23266 59 34 EV 23266 59 35 0.0253 23266 59 36 ENDCOMMON 3 0 23266 59 37 DATA 1 1 23266 59 38 DATA 23266 59 39 B 23266 59 40 2.06 23266 59 41 ENDDATA 3 0 23266 59 42 ENDSUBENT 41 0 23266 5999999 SUBENT 23266060 20230215 231423266 60 1 BIB 9 26 23266 60 2 REACTION 1((30-ZN-64(N,G)30-ZN-65,,RI,,AV)// 23266 60 3 (30-ZN-64(N,G)30-ZN-65,,SIG,,AV)) 23266 60 4 2((30-ZN-64(N,G)30-ZN-65,,RI)// 23266 60 5 (30-ZN-64(N,G)30-ZN-65,,SIG)) 23266 60 6 Q0 value (ratio of resonance integral to thermal 23266 60 7 neutron activation cross-section) 23266 60 8 SAMPLE - Provider - Goodfellow 23266 60 9 Matrix - Foil 23266 60 10 Elemental content, % weight - 99.95 23266 60 11 Average sample thickness, mm - 0.025 23266 60 12 (30-ZN-64,NAT=0.4917) 49.17+-0.75 % 23266 60 13 METHOD Measurement at channels S84, Y4, X26 . 23266 60 14 DECAY-DATA (30-ZN-65,244.3D,DG,511.0,0.02842,DG,1115.5,0.5022) 23266 60 15 ANALYSIS The Q0 factor was determined by 23266 60 16 1- the classical method: through the weighted mean and 23266 60 17 observed standard deviation of the 3 irradiation 23266 60 18 channels employed (Y4, S84, X26), when inputting Er 23266 60 19 factors from the literature. 23266 60 20 2- the a-vector method: through the parameters 23266 60 21 (m, b) --> determination of the value as well. 23266 60 22 ADD-RES Effective resonance Energy was defined by a-vect23266 60 23 method to be 2711.eV ( +-14%, 2sigma). 23266 60 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 60 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 60 26 1(DEP,23266061) Directly measured data . 23266 60 27 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 60 28 ENDBIB 26 0 23266 60 29 COMMON 2 3 23266 60 30 EN-MIN-NM EN-DN 23266 60 31 EV EV 23266 60 32 0.55 0.0253 23266 60 33 ENDCOMMON 3 0 23266 60 34 DATA 4 1 23266 60 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 60 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266 60 37 1.90 2. 1.90 2. 23266 60 38 ENDDATA 3 0 23266 60 39 ENDSUBENT 38 0 23266 6099999 SUBENT 23266061 20141210 224123266 61 1 BIB 7 29 23266 61 2 REACTION ((30-ZN-64(N,G)30-ZN-65,,RI)// 23266 61 3 (30-ZN-64(N,G)30-ZN-65,,SIG)) 23266 61 4 Q0 value (ratio of resonance integral to thermal 23266 61 5 neutron activation cross-section) 23266 61 6 SAMPLE - Provider - Goodfellow 23266 61 7 Matrix - Foil 23266 61 8 Elemental content, % weight - 99.95 23266 61 9 Average sample thickness, mm - 0.025 23266 61 10 (30-ZN-64,NAT=0.4917) 49.17+-0.75 % 23266 61 11 DECAY-DATA (30-ZN-65,244.3D,DG,511.0,0.02842,DG,1115.5,0.5022) 23266 61 12 FLAG Measurement at channels 23266 61 13 (1.) S84, 23266 61 14 (2.) Y4 23266 61 15 (3.) X26 23266 61 16 ANALYSIS The Q0 factor was determined by the classical method 23266 61 17 when inputting effective resonance energy factors 23266 61 18 from the literature. 23266 61 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 61 20 uncertainties ( 1 sigma) from: 23266 61 21 (ERR-1) alpha factor, 23266 61 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 61 23 epithermal flux for gold, 23266 61 24 (ERR-3) effective resonance energy Er, 23266 61 25 (ERR-4) Cd transmission factor FCd 23266 61 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 61 27 bare and Cd-covered sample. 23266 61 28 (ERR-S) Standard deviation. 23266 61 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 61 30 (COREL,23266060) Average data . 23266 61 31 ENDBIB 29 0 23266 61 32 COMMON 2 3 23266 61 33 EN-MIN-NM EN-DN 23266 61 34 EV EV 23266 61 35 0.55 0.0253 23266 61 36 ENDCOMMON 3 0 23266 61 37 DATA 9 3 23266 61 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 61 39 ERR-5 ERR-SYS FLAG 23266 61 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 61 41 PER-CENT PER-CENT NO-DIM 23266 61 42 1.89 0.55 1.65 1.4 0.4 0.6 23266 61 43 0.65 2.35 1. 23266 61 44 1.93 1.5 1.0 1.1 0.3 0.55 23266 61 45 0.65 1.75 2. 23266 61 46 1.85 3.1 1.65 1.8 0.4 0.6 23266 61 47 0.65 2.65 3. 23266 61 48 ENDDATA 10 0 23266 61 49 ENDSUBENT 48 0 23266 6199999 SUBENT 23266062 20230215 231423266 62 1 BIB 5 11 23266 62 2 REACTION (30-ZN-64(N,G)30-ZN-65,,SIG,,AV) 23266 62 3 SIG-0 - the average thermal neutron cross-section . 23266 62 4 for neutrons at an average energy of E0=25.3 meV 23266 62 5 or velocity v0=2200 m/s. 23266 62 6 ANALYSIS Derived from directly measured data. 23266 62 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 62 8 Uncertainty on exp. SIG-0 value comes from to the 23266 62 9 observed SD between gamma-lines. 23266 62 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 62 11 (DEP,23266063) Directly measured data. 23266 62 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 62 13 ENDBIB 11 0 23266 62 14 COMMON 1 3 23266 62 15 EN 23266 62 16 EV 23266 62 17 0.0253 23266 62 18 ENDCOMMON 3 0 23266 62 19 DATA 2 1 23266 62 20 DATA DATA-ERR 23266 62 21 B B 23266 62 22 0.717 0.007 23266 62 23 ENDDATA 3 0 23266 62 24 ENDSUBENT 23 0 23266 6299999 SUBENT 23266063 20141210 224123266 63 1 BIB 8 23 23266 63 2 REACTION (30-ZN-64(N,G)30-ZN-65,,SIG) 23266 63 3 Directly measured thermal neutron cross-section SIG-0 23266 63 4 SAMPLE - Provider - Goodfellow 23266 63 5 Matrix - Foil 23266 63 6 Elemental content, % weight - 99.95 23266 63 7 Average sample thickness, mm - 0.025 23266 63 8 (30-ZN-64,NAT=0.4917) 49.17+-0.75 % 23266 63 9 DECAY-DATA ((1.)30-ZN-65,244.3D,DG,511.0,0.02842) 23266 63 10 ((2.)30-ZN-65,244.3D,DG,1115.5,0.5022) 23266 63 11 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 63 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 63 13 extrapolated with aid of the k0-definition, atomic 23266 63 14 weight, isotopic composition, the gamma intensities 23266 63 15 values. 23266 63 16 Defined according to their ADS(activation decay scheme,23266 63 17 including decay branching factors). 23266 63 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266 63 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 63 20 511.0 3.20E-4 (+-2.0%) 23266 63 21 1115.5 5.66E-3 (+-1.0%) 23266 63 22 ERR-ANALYS Uncertainty is not given. 23266 63 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 63 24 (COREL,23266062) Average data 23266 63 25 ENDBIB 23 0 23266 63 26 COMMON 1 3 23266 63 27 EN 23266 63 28 EV 23266 63 29 0.0253 23266 63 30 ENDCOMMON 3 0 23266 63 31 DATA 2 2 23266 63 32 DATA DECAY-FLAG 23266 63 33 B NO-DIM 23266 63 34 0.717 1. 23266 63 35 0.717 2. 23266 63 36 ENDDATA 4 0 23266 63 37 ENDSUBENT 36 0 23266 6399999 SUBENT 23266064 20230215 231423266 64 1 BIB 9 26 23266 64 2 REACTION 1((30-ZN-68(N,G)30-ZN-69-M,,RI,,AV)// 23266 64 3 (30-ZN-68(N,G)30-ZN-69-M,,SIG,,AV)) 23266 64 4 2((30-ZN-68(N,G)30-ZN-69-M,,RI)// 23266 64 5 (30-ZN-68(N,G)30-ZN-69-M,,SIG)) 23266 64 6 Q0 value (ratio of resonance integral to thermal 23266 64 7 neutron activation cross-section) 23266 64 8 SAMPLE - Provider - Goodfellow 23266 64 9 Matrix - Foil 23266 64 10 Elemental content, % weight - 99.95 23266 64 11 Average sample thickness, mm - 0.025 23266 64 12 (30-ZN-68,NAT=0.1845) 18.45+-0.63 % 23266 64 13 METHOD Measurement at channels S84, Y4, X26 . 23266 64 14 DECAY-DATA (30-ZN-69-M,13.76HR,DG,438.6,0.9477) 23266 64 15 ANALYSIS The Q0 factor was determined by 23266 64 16 1- the classical method: through the weighted mean and 23266 64 17 observed standard deviation of the 3 irradiation 23266 64 18 channels employed (Y4, S84, X26), when inputting Er 23266 64 19 factors from the literature. 23266 64 20 2- the a-vector method: through the parameters 23266 64 21 (m, b) --> determination of the value as well. 23266 64 22 ADD-RES Effective resonance Energy was defined by a-vect23266 64 23 method to be 737.eV ( +-8%, 2sigma). 23266 64 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 64 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 64 26 1(DEP,23266065) Directly measured data . 23266 64 27 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 64 28 ENDBIB 26 0 23266 64 29 COMMON 2 3 23266 64 30 EN-MIN-NM EN-DN 23266 64 31 EV EV 23266 64 32 0.55 0.0253 23266 64 33 ENDCOMMON 3 0 23266 64 34 DATA 4 1 23266 64 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 64 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266 64 37 3.21 1. 3.24 2. 23266 64 38 ENDDATA 3 0 23266 64 39 ENDSUBENT 38 0 23266 6499999 SUBENT 23266065 20141210 224123266 65 1 BIB 7 29 23266 65 2 REACTION ((30-ZN-68(N,G)30-ZN-69-M,,RI)// 23266 65 3 (30-ZN-68(N,G)30-ZN-69-M,,SIG)) 23266 65 4 Q0 value (ratio of resonance integral to thermal 23266 65 5 neutron activation cross-section) 23266 65 6 SAMPLE - Provider - Goodfellow 23266 65 7 Matrix - Foil 23266 65 8 Elemental content, % weight - 99.95 23266 65 9 Average sample thickness, mm - 0.025 23266 65 10 (30-ZN-69-M,NAT=0.1845) 18.45+-0.63 % 23266 65 11 DECAY-DATA (30-ZN-69-M,13.76HR,DG,438.6,0.9477) 23266 65 12 FLAG Measurement at channels 23266 65 13 (1.) S84, 23266 65 14 (2.) Y4 23266 65 15 (3.) X26 23266 65 16 ANALYSIS The Q0 factor was determined by the classical method 23266 65 17 when inputting effective resonance energy factors 23266 65 18 from the literature. 23266 65 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 65 20 uncertainties ( 1 sigma) from: 23266 65 21 (ERR-1) alpha factor, 23266 65 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 65 23 epithermal flux for gold, 23266 65 24 (ERR-3) effective resonance energy Er, 23266 65 25 (ERR-4) Cd transmission factor FCd 23266 65 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 65 27 bare and Cd-covered sample. 23266 65 28 (ERR-S) Standard deviation. 23266 65 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 65 30 (COREL,23266064) Average data . 23266 65 31 ENDBIB 29 0 23266 65 32 COMMON 2 3 23266 65 33 EN-MIN-NM EN-DN 23266 65 34 EV EV 23266 65 35 0.55 0.0253 23266 65 36 ENDCOMMON 3 0 23266 65 37 DATA 9 3 23266 65 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 65 39 ERR-5 ERR-SYS FLAG 23266 65 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 65 41 PER-CENT PER-CENT NO-DIM 23266 65 42 3.24 0.6 1.3 1.55 0.1 0.6 23266 65 43 0.65 2.2 1. 23266 65 44 3.22 0.35 0.7 1.1 0.1 0.55 23266 65 45 0.65 1.65 2. 23266 65 46 3.17 2.5 1.35 1.65 0.15 0.6 23266 65 47 0.65 2.3 3. 23266 65 48 ENDDATA 10 0 23266 65 49 ENDSUBENT 48 0 23266 6599999 SUBENT 23266066 20230215 231423266 66 1 BIB 6 12 23266 66 2 REACTION (30-ZN-68(N,G)30-ZN-69-M,,SIG,,AV) 23266 66 3 SIG-0 - the average thermal neutron cross-section . 23266 66 4 for neutrons at an average energy of E0=25.3 meV 23266 66 5 or velocity v0=2200 m/s. 23266 66 6 DECAY-DATA (30-ZN-69-M,13.76HR) 23266 66 7 ANALYSIS Derived from directly measured data. 23266 66 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 66 9 Uncertainty on exp. SIG-0 value comes from to the 23266 66 10 observed SD between gamma-lines. 23266 66 11 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 66 12 (DEP,23266067) Directly measured data. 23266 66 13 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 66 14 ENDBIB 12 0 23266 66 15 COMMON 1 3 23266 66 16 EN 23266 66 17 EV 23266 66 18 0.0253 23266 66 19 ENDCOMMON 3 0 23266 66 20 DATA 2 1 23266 66 21 DATA DATA-ERR 23266 66 22 B B 23266 66 23 0.071 0.001 23266 66 24 ENDDATA 3 0 23266 66 25 ENDSUBENT 24 0 23266 6699999 SUBENT 23266067 20141210 224123266 67 1 BIB 8 21 23266 67 2 REACTION (30-ZN-68(N,G)30-ZN-69-M,,SIG) 23266 67 3 Directly measured thermal neutron cross-section SIG-0 23266 67 4 SAMPLE - Provider - Goodfellow 23266 67 5 Matrix - Foil 23266 67 6 Elemental content, % weight - 99.95 23266 67 7 Average sample thickness, mm - 0.025 23266 67 8 (30-ZN-69-M,NAT=0.1845) 18.45+-0.63 % 23266 67 9 DECAY-DATA (30-ZN-69-M,13.76HR,DG,438.6,0.9477) 23266 67 10 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 67 11 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 67 12 extrapolated with aid of the k0-definition, atomic 23266 67 13 weight, isotopic composition, the gamma intensities 23266 67 14 values. 23266 67 15 Defined according to their ADS(activation decay scheme,23266 67 16 including decay branching factors). 23266 67 17 ADD-RES Measured k0-values with one-sigma uncertainty 23266 67 18 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 67 19 438.6 3.98E-4 (+-2.0%) 23266 67 20 ERR-ANALYS Uncertainty is not given. 23266 67 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 67 22 (COREL,23266066) Average data 23266 67 23 ENDBIB 21 0 23266 67 24 COMMON 1 3 23266 67 25 EN 23266 67 26 EV 23266 67 27 0.0253 23266 67 28 ENDCOMMON 3 0 23266 67 29 DATA 1 1 23266 67 30 DATA 23266 67 31 B 23266 67 32 0.071 23266 67 33 ENDDATA 3 0 23266 67 34 ENDSUBENT 33 0 23266 6799999 SUBENT 23266068 20230215 231423266 68 1 BIB 9 48 23266 68 2 REACTION 1((31-GA-71(N,G)31-GA-72,,RI,,AV)// 23266 68 3 (31-GA-71(N,G)31-GA-72,,SIG,,AV)) 23266 68 4 2((31-GA-71(N,G)31-GA-72,,RI)// 23266 68 5 (31-GA-71(N,G)31-GA-72,,SIG)) 23266 68 6 Q0 value (ratio of resonance integral to thermal 23266 68 7 neutron activation cross-section) 23266 68 8 SAMPLE - Provider - IRMM 23266 68 9 Matrix - Wire,Al alloy 23266 68 10 Elemental content, % weight - 1. 23266 68 11 Average sample thickness, mm - 1. 23266 68 12 (31-GA-71,NAT=0.39892) 39.892+-0.008 % 23266 68 13 METHOD Measurement at channels S84, Y4, X26 . 23266 68 14 DECAY-DATA (31-GA-72,14.10HR,DG,289.5,0.00199, 23266 68 15 DG,381.7,0.00304, 23266 68 16 DG,428.6,0.00216, 23266 68 17 DG,600.9,0.05822, 23266 68 18 DG,630.0,0.2613, 23266 68 19 DG,786.5,0.0334, 23266 68 20 DG,810.3,0.02087, 23266 68 21 DG,834.1,0.9545, 23266 68 22 DG,894.3,0.10136, 23266 68 23 DG,970.8,0.01103, 23266 68 24 DG,1050.8,0.06991, 23266 68 25 DG,1215.1,0.00811, 23266 68 26 DG,1230.9,0.01425, 23266 68 27 DG,1260.1,0.01169, 23266 68 28 DG,1276.8,0.01587, 23266 68 29 DG,1464.1,0.03609, 23266 68 30 DG,1596.7,0.0439, 23266 68 31 DG,1862.0,0.0541, 23266 68 32 DG,2201.6,0.2687, 23266 68 33 DG,2491.0,0.0773, 23266 68 34 DG,2507.7,0.1333) 23266 68 35 14.10+-0.02 hr 23266 68 36 ANALYSIS The Q0 factor was determined by 23266 68 37 1- the classical method: through the weighted mean and 23266 68 38 observed standard deviation of the 3 irradiation 23266 68 39 channels employed (Y4, S84, X26), when inputting Er 23266 68 40 factors from the literature. 23266 68 41 2- the a-vector method: through the parameters 23266 68 42 (m, b) --> determination of the value as well. 23266 68 43 ADD-RES Effective resonance Energy was defined by a-vect23266 68 44 method to be 142.eV ( +-4%, 2sigma). 23266 68 45 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 68 46 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 68 47 1(DEP,23266069) Directly measured data . 23266 68 48 HISTORY (20180202A) M.M. DATA misprint was corrected 23266 68 49 (20230215A) SD: SF8=AV added to REACTION codes. 23266 68 50 ENDBIB 48 0 23266 68 51 COMMON 2 3 23266 68 52 EN-MIN-NM EN-DN 23266 68 53 EV EV 23266 68 54 0.55 0.0253 23266 68 55 ENDCOMMON 3 0 23266 68 56 DATA 4 1 23266 68 57 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 68 58 NO-DIM PER-CENT NO-DIM PER-CENT 23266 68 59 6.94 0.5 6.89 2. 23266 68 60 ENDDATA 3 0 23266 68 61 ENDSUBENT 60 0 23266 6899999 SUBENT 23266069 20141210 224123266 69 1 BIB 7 37 23266 69 2 REACTION ((31-GA-71(N,G)31-GA-72,,RI)// 23266 69 3 (31-GA-71(N,G)31-GA-72,,SIG)) 23266 69 4 Q0 value (ratio of resonance integral to thermal 23266 69 5 neutron activation cross-section) 23266 69 6 SAMPLE - Provider - IRMM 23266 69 7 Matrix - Wire,Al alloy 23266 69 8 Elemental content, % weight - 1. 23266 69 9 Average sample thickness, mm - 1. 23266 69 10 (31-GA-71,NAT=0.39892) 39.892+-0.008 % 23266 69 11 DECAY-DATA (31-GA-72,14.10HR,DG,289.5,0.00199,DG,381.7,0.00304, 23266 69 12 DG,428.6,0.00216,DG,600.9,0.05822,DG,630.0,0.2613, 23266 69 13 DG,786.5,0.0334,DG,810.3,0.02087,DG,834.1,0.9545, 23266 69 14 DG,894.3,0.10136,DG,970.8,0.01103,DG,1050.8,0.06991, 23266 69 15 DG,1215.1,0.00811,DG,1230.9,0.01425,DG,1260.1,0.01169, 23266 69 16 DG,1276.8,0.01587,DG,1464.1,0.03609,DG,1596.7,0.0439, 23266 69 17 DG,1862.0,0.0541,DG,2201.6,0.2687,DG,2491.0,0.0773, 23266 69 18 DG,2507.7,0.1333) 23266 69 19 14.10+-0.02 hr 23266 69 20 FLAG Measurement at channels 23266 69 21 (1.) S84, 23266 69 22 (2.) Y4 23266 69 23 (3.) X26 23266 69 24 ANALYSIS The Q0 factor was determined by the classical method 23266 69 25 when inputting effective resonance energy factors 23266 69 26 from the literature. 23266 69 27 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 69 28 uncertainties ( 1 sigma) from: 23266 69 29 (ERR-1) alpha factor, 23266 69 30 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 69 31 epithermal flux for gold, 23266 69 32 (ERR-3) effective resonance energy Er, 23266 69 33 (ERR-4) Cd transmission factor FCd 23266 69 34 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 69 35 bare and Cd-covered sample. 23266 69 36 (ERR-S) Standard deviation. 23266 69 37 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 69 38 (COREL,23266068) Average data . 23266 69 39 ENDBIB 37 0 23266 69 40 COMMON 2 3 23266 69 41 EN-MIN-NM EN-DN 23266 69 42 EV EV 23266 69 43 0.55 0.0253 23266 69 44 ENDCOMMON 3 0 23266 69 45 DATA 9 3 23266 69 46 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 69 47 ERR-5 ERR-SYS FLAG 23266 69 48 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 69 49 PER-CENT PER-CENT NO-DIM 23266 69 50 6.89 1.4 1.5 1.5 0.05 0.7 23266 69 51 0.85 2.4 1. 23266 69 52 6.97 1.65 0.7 1.3 0.45 0.6 23266 69 53 0.7 1.8 2. 23266 69 54 6.94 2.95 1.4 1.35 0.7 0.55 23266 69 55 0.65 2.25 3. 23266 69 56 ENDDATA 10 0 23266 69 57 ENDSUBENT 56 0 23266 6999999 SUBENT 23266070 20230215 231423266 70 1 BIB 5 11 23266 70 2 REACTION (31-GA-71(N,G)31-GA-72,,SIG,,AV) 23266 70 3 SIG-0 - the average thermal neutron cross-section . 23266 70 4 for neutrons at an average energy of E0=25.3 meV 23266 70 5 or velocity v0=2200 m/s. 23266 70 6 ANALYSIS Derived from directly measured data. 23266 70 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 70 8 Uncertainty on exp. SIG-0 value comes from to the 23266 70 9 observed SD between gamma-lines. 23266 70 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 70 11 (DEP,23266071) Directly measured data. 23266 70 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 70 13 ENDBIB 11 0 23266 70 14 COMMON 1 3 23266 70 15 EN 23266 70 16 EV 23266 70 17 0.0253 23266 70 18 ENDCOMMON 3 0 23266 70 19 DATA 2 1 23266 70 20 DATA DATA-ERR 23266 70 21 B B 23266 70 22 4.61 0.04 23266 70 23 ENDDATA 3 0 23266 70 24 ENDSUBENT 23 0 23266 7099999 SUBENT 23266071 20141210 224123266 71 1 BIB 8 62 23266 71 2 REACTION (31-GA-71(N,G)31-GA-72,,SIG) 23266 71 3 Directly measured thermal neutron cross-section SIG-0 23266 71 4 SAMPLE - Provider - IRMM 23266 71 5 Matrix - Wire,Al alloy 23266 71 6 Elemental content, % weight - 1. 23266 71 7 Average sample thickness, mm - 1. 23266 71 8 (31-GA-71,NAT=0.39892) 39.892+-0.008 % 23266 71 9 DECAY-DATA ((1.)31-GA-72,14.10HR,DG,289.5,0.00199) 23266 71 10 ((2.)31-GA-72,14.10HR,DG,381.7,0.00304) 23266 71 11 ((3.)31-GA-72,14.10HR,DG,428.6,0.00216) 23266 71 12 ((4.)31-GA-72,14.10HR,DG,600.9,0.05822) 23266 71 13 ((5.)31-GA-72,14.10HR,DG,630.0,0.2613) 23266 71 14 ((6.)31-GA-72,14.10HR,DG,786.5,0.0334) 23266 71 15 ((7.)31-GA-72,14.10HR,DG,810.3,0.02087) 23266 71 16 ((8.)31-GA-72,14.10HR,DG,834.1,0.9545) 23266 71 17 ((9.)31-GA-72,14.10HR,DG,894.3,0.10136) 23266 71 18 ((10.)31-GA-72,14.10HR,DG,970.8,0.01103) 23266 71 19 ((11.)31-GA-72,14.10HR,DG,1050.8,0.06991) 23266 71 20 ((12.)31-GA-72,14.10HR,DG,1215.1,0.00811) 23266 71 21 ((13.)31-GA-72,14.10HR,DG,1230.9,0.01425) 23266 71 22 ((14.)31-GA-72,14.10HR,DG,1260.1,0.01169) 23266 71 23 ((15.)31-GA-72,14.10HR,DG,1276.8,0.01587) 23266 71 24 ((16.)31-GA-72,14.10HR,DG,1464.1,0.03609) 23266 71 25 ((17.)31-GA-72,14.10HR,DG,1596.7,0.0439) 23266 71 26 ((18.)31-GA-72,14.10HR,DG,1862.0,0.0541) 23266 71 27 ((19.)31-GA-72,14.10HR,DG,2201.6,0.2687) 23266 71 28 ((20.)31-GA-72,14.10HR,DG,2491.0,0.0773) 23266 71 29 ((21.)31-GA-72,14.10HR,DG,2507.7,0.1333) 23266 71 30 14.10+-0.02 hr 23266 71 31 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 71 32 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 71 33 extrapolated with aid of the k0-definition, atomic 23266 71 34 weight, isotopic composition, the gamma intensities 23266 71 35 values. 23266 71 36 Defined according to their ADS(activation decay scheme,23266 71 37 including decay branching factors). 23266 71 38 ADD-RES Measured k0-values with one-sigma uncertainty 23266 71 39 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 71 40 289.5 1.09E-4 (+-2.3%) 23266 71 41 381.7 1.65E-4 (+-0.7%) 23266 71 42 428.6 1.17E-4 (+-2.6%) 23266 71 43 600.9 3.18E-3 (+-1.4%) 23266 71 44 630.0 1.45E-2 (+-0.8%) 23266 71 45 786.5 1.84E-3 (+-1.3%) 23266 71 46 810.3 1.15E-3 (+-1.2%) 23266 71 47 834.1 5.26E-2 (+-0.6%) 23266 71 48 894.3 5.57E-3 (+-1.2%) 23266 71 49 970.8 6.10E-4 (+-0.4%) 23266 71 50 1050.8 3.85E-3 (+-0.6%) 23266 71 51 1215.1 4.44E-4 (+-2.1%) 23266 71 52 1230.9 7.95E-4 (+-2.4%) 23266 71 53 1260.1 6.37E-4 (+-1.5%) 23266 71 54 1276.8 8.84E-4 (+-0.8%) 23266 71 55 1464.1 2.01E-3 (+-0.7%) 23266 71 56 1596.7 2.42E-3 (+-0.3%) 23266 71 57 1862.0 3.01E-3 (+-0.6%) 23266 71 58 2201.6 1.50E-2 (+-0.7%) 23266 71 59 2491.0 4.28E-3 (+-0.3%) 23266 71 60 2507.7 7.43E-3 (+-0.4%) 23266 71 61 ERR-ANALYS Uncertainty is not given. 23266 71 62 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 71 63 (COREL,23266067) Average data 23266 71 64 ENDBIB 62 0 23266 71 65 COMMON 1 3 23266 71 66 EN 23266 71 67 EV 23266 71 68 0.0253 23266 71 69 ENDCOMMON 3 0 23266 71 70 DATA 2 21 23266 71 71 DATA DECAY-FLAG 23266 71 72 B NO-DIM 23266 71 73 4.58 1. 23266 71 74 4.55 2. 23266 71 75 4.55 3. 23266 71 76 4.57 4. 23266 71 77 4.64 5. 23266 71 78 4.60 6. 23266 71 79 4.60 7. 23266 71 80 4.61 8. 23266 71 81 4.60 9. 23266 71 82 4.63 10. 23266 71 83 4.61 11. 23266 71 84 4.58 12. 23266 71 85 4.67 13. 23266 71 86 4.56 14. 23266 71 87 4.66 15. 23266 71 88 4.66 16. 23266 71 89 4.62 17. 23266 71 90 4.65 18. 23266 71 91 4.68 19. 23266 71 92 4.63 20. 23266 71 93 4.66 21. 23266 71 94 ENDDATA 23 0 23266 71 95 ENDSUBENT 94 0 23266 7199999 SUBENT 23266072 20230215 231423266 72 1 BIB 9 33 23266 72 2 REACTION 1((33-AS-75(N,G)33-AS-76,,RI,,AV)// 23266 72 3 (33-AS-75(N,G)33-AS-76,,SIG,,AV)) 23266 72 4 2((33-AS-75(N,G)33-AS-76,,RI)// 23266 72 5 (33-AS-75(N,G)33-AS-76,,SIG)) 23266 72 6 Q0 value (ratio of resonance integral to thermal 23266 72 7 neutron activation cross-section) 23266 72 8 SAMPLE - Provider - Alfa Aesar 23266 72 9 Matrix - Liquid on paper 23266 72 10 Elemental content, % weight - 0.1 23266 72 11 Average sample thickness, mm - 1.5 23266 72 12 - Provider - NIST 23266 72 13 Elemental content, % weight - 1. 23266 72 14 (33-AS-75,NAT=1.00) 23266 72 15 METHOD Measurement at channels S84, Y4, X26 . 23266 72 16 DECAY-DATA (33-AS-76,26.24HR,DG,559.1,0.45,DG,563.2,0.012, 23266 72 17 DG,571.5,0.0014,DG,657.1,0.062,DG,665.3,0.004, 23266 72 18 DG,740.1,0.00117,DG,771.7,0.00122,DG,867.6,0.00131, 23266 72 19 DG,1212.9,0.0144,DG,1228.5,0.0122,DG,1439.1,0.00279, 23266 72 20 DG,1216.1,0.0342,DG,2096.3,0.0055,DG,1129.9,0.00126, 23266 72 21 DG,1453.6,0.00108,DG,1787.7,0.00293) 23266 72 22 ANALYSIS The Q0 factor was determined by 23266 72 23 1- the classical method: through the weighted mean and 23266 72 24 observed standard deviation of the 3 irradiation 23266 72 25 channels employed (Y4, S84, X26), when inputting Er 23266 72 26 factors from the literature. 23266 72 27 2- the a-vector method: through the parameters 23266 72 28 (m, b) --> determination of the value as well. 23266 72 29 ADD-RES Effective resonance Energy was defined by a-vect23266 72 30 method to be 121.eV ( +-6%, 2sigma). 23266 72 31 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 72 32 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 72 33 1(DEP,23266073) Directly measured data . 23266 72 34 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 72 35 ENDBIB 33 0 23266 72 36 COMMON 2 3 23266 72 37 EN-MIN-NM EN-DN 23266 72 38 EV EV 23266 72 39 0.55 0.0253 23266 72 40 ENDCOMMON 3 0 23266 72 41 DATA 4 1 23266 72 42 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 72 43 NO-DIM PER-CENT NO-DIM PER-CENT 23266 72 44 15.0 1. 15.1 2. 23266 72 45 ENDDATA 3 0 23266 72 46 ENDSUBENT 45 0 23266 7299999 SUBENT 23266073 20141210 224123266 73 1 BIB 7 36 23266 73 2 REACTION ((33-AS-75(N,G)33-AS-76,,RI)// 23266 73 3 (33-AS-75(N,G)33-AS-76,,SIG)) 23266 73 4 Q0 value (ratio of resonance integral to thermal 23266 73 5 neutron activation cross-section) 23266 73 6 SAMPLE - Provider - Alfa Aesar 23266 73 7 Matrix - Liquid on paper 23266 73 8 Elemental content, % weight - 0.1 23266 73 9 Average sample thickness, mm - 1.5 23266 73 10 - Provider - NIST 23266 73 11 Elemental content, % weight - 1. 23266 73 12 (33-AS-75,NAT=1.00) 23266 73 13 DECAY-DATA (33-AS-76,26.24HR,DG,559.1,0.45,DG,563.2,0.012, 23266 73 14 DG,571.5,0.0014,DG,657.1,0.062,DG,665.3,0.004, 23266 73 15 DG,740.1,0.00117,DG,771.7,0.00122,DG,867.6,0.00131, 23266 73 16 DG,1212.9,0.0144,DG,1228.5,0.0122,DG,1439.1,0.00279, 23266 73 17 DG,1216.1,0.0342,DG,2096.3,0.0055,DG,1129.9,0.00126, 23266 73 18 DG,1453.6,0.00108,DG,1787.7,0.00293) 23266 73 19 FLAG Measurement at channels 23266 73 20 (1.) S84, 23266 73 21 (2.) Y4 23266 73 22 (3.) X26 23266 73 23 ANALYSIS The Q0 factor was determined by the classical method 23266 73 24 when inputting effective resonance energy factors 23266 73 25 from the literature. 23266 73 26 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 73 27 uncertainties ( 1 sigma) from: 23266 73 28 (ERR-1) alpha factor, 23266 73 29 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 73 30 epithermal flux for gold, 23266 73 31 (ERR-3) effective resonance energy Er, 23266 73 32 (ERR-4) Cd transmission factor FCd 23266 73 33 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 73 34 bare and Cd-covered sample. 23266 73 35 (ERR-S) Standard deviation. 23266 73 36 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 73 37 (COREL,23266072) Average data . 23266 73 38 ENDBIB 36 0 23266 73 39 COMMON 2 3 23266 73 40 EN-MIN-NM EN-DN 23266 73 41 EV EV 23266 73 42 0.55 0.0253 23266 73 43 ENDCOMMON 3 0 23266 73 44 DATA 9 3 23266 73 45 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 73 46 ERR-5 ERR-SYS FLAG 23266 73 47 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 73 48 PER-CENT PER-CENT NO-DIM 23266 73 49 15.0 0.15 1.4 1.5 0.15 1.0 23266 73 50 1.2 2.6 1. 23266 73 51 15.1 0.25 1.0 1.3 0.9 0.65 23266 73 52 0.8 2.15 2. 23266 73 53 14.8 2.05 1.3 1.3 1.1 0.55 23266 73 54 0.7 2.3 3. 23266 73 55 ENDDATA 10 0 23266 73 56 ENDSUBENT 55 0 23266 7399999 SUBENT 23266074 20230215 231423266 74 1 BIB 5 11 23266 74 2 REACTION (33-AS-75(N,G)33-AS-76,,SIG,,AV) 23266 74 3 SIG-0 - the average thermal neutron cross-section . 23266 74 4 for neutrons at an average energy of E0=25.3 meV 23266 74 5 or velocity v0=2200 m/s. 23266 74 6 ANALYSIS Derived from directly measured data. 23266 74 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 74 8 Uncertainty on exp. SIG-0 value comes from to the 23266 74 9 observed SD between gamma-lines. 23266 74 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 74 11 (DEP,23266075) Directly measured data. 23266 74 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 74 13 ENDBIB 11 0 23266 74 14 COMMON 1 3 23266 74 15 EN 23266 74 16 EV 23266 74 17 0.0253 23266 74 18 ENDCOMMON 3 0 23266 74 19 DATA 2 1 23266 74 20 DATA DATA-ERR 23266 74 21 B B 23266 74 22 3.84 0.11 23266 74 23 ENDDATA 3 0 23266 74 24 ENDSUBENT 23 0 23266 7499999 SUBENT 23266075 20141210 224123266 75 1 BIB 8 53 23266 75 2 REACTION (33-AS-75(N,G)33-AS-76,,SIG) 23266 75 3 Directly measured thermal neutron cross-section SIG-0 23266 75 4 SAMPLE - Provider - Alfa Aesar 23266 75 5 Matrix - Liquid on paper 23266 75 6 Elemental content, % weight - 0.1 23266 75 7 Average sample thickness, mm - 1.5 23266 75 8 - Provider - NIST 23266 75 9 Elemental content, % weight - 1. 23266 75 10 (33-AS-75,NAT=1.00) 23266 75 11 DECAY-DATA ((1.)33-AS-76,26.24HR,DG,559.1,0.45) 23266 75 12 ((2.)33-AS-76,26.24HR,DG,563.2,0.012) 23266 75 13 ((3.)33-AS-76,26.24HR,DG,571.5,0.0014) 23266 75 14 ((4.)33-AS-76,26.24HR,DG,657.1,0.062) 23266 75 15 ((5.)33-AS-76,26.24HR,DG,665.3,0.004) 23266 75 16 ((6.)33-AS-76,26.24HR,DG,740.1,0.00117) 23266 75 17 ((7.)33-AS-76,26.24HR,DG,771.7,0.00122) 23266 75 18 ((8.)33-AS-76,26.24HR,DG,867.6,0.00131) 23266 75 19 ((9.)33-AS-76,26.24HR,DG,1212.9,0.0144) 23266 75 20 ((10.)33-AS-76,26.24HR,DG,1228.5,0.0122) 23266 75 21 ((11.)33-AS-76,26.24HR,DG,1439.1,0.00279) 23266 75 22 ((12.)33-AS-76,26.24HR,DG,1216.1,0.0342) 23266 75 23 ((13.)33-AS-76,26.24HR,DG,2096.3,0.0055) 23266 75 24 ((14.)33-AS-76,26.24HR,DG,1129.9,0.00126) 23266 75 25 ((15.)33-AS-76,26.24HR,DG,1453.6,0.00108) 23266 75 26 ((16.)33-AS-76,26.24HR,DG,1787.7,0.00293) 23266 75 27 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 75 28 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 75 29 extrapolated with aid of the k0-definition, atomic 23266 75 30 weight, isotopic composition, the gamma intensities 23266 75 31 values. 23266 75 32 Defined according to their ADS(activation decay scheme,23266 75 33 including decay branching factors). 23266 75 34 ADD-RES Measured k0-values with one-sigma uncertainty 23266 75 35 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 75 36 559.1 4.86E-2 (+-0.3%) 23266 75 37 563.2 1.33E-3 (+-1.3%) 23266 75 38 571.5 1.51E-4 (+-1.8%) 23266 75 39 657.1 6.75E-3 (+-0.1%) 23266 75 40 665.3 4.62E-4 (+-0.7%) 23266 75 41 740.1 1.28E-4 (+-1.0%) 23266 75 42 771.7 1.24E-4 (+-1.1%) 23266 75 43 867.6 1.40E-4 (+-1.6%) 23266 75 44 1212.9 1.54E-3 (+-0.9%) 23266 75 45 1228.5 1.28E-3 (+-0.9%) 23266 75 46 1439.1 2.96E-4 (+-1.1%) 23266 75 47 1216.1 3.66E-3 (+-0.9%) 23266 75 48 2096.3 6.05E-4 (+-1.2%) 23266 75 49 1129.9 1.39E-4 (+-1.6%) 23266 75 50 1453.6 1.15E-4 (+-0.8%) 23266 75 51 1787.7 3.12E-4 (+-1.4%) 23266 75 52 ERR-ANALYS Uncertainty is not given. 23266 75 53 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 75 54 (COREL,23266074) Average data 23266 75 55 ENDBIB 53 0 23266 75 56 COMMON 1 3 23266 75 57 EN 23266 75 58 EV 23266 75 59 0.0253 23266 75 60 ENDCOMMON 3 0 23266 75 61 DATA 2 16 23266 75 62 DATA DECAY-FLAG 23266 75 63 B NO-DIM 23266 75 64 3.88 1. 23266 75 65 3.99 2. 23266 75 66 3.87 3. 23266 75 67 3.90 4. 23266 75 68 4.14 5. 23266 75 69 3.91 6. 23266 75 70 3.66 7. 23266 75 71 3.83 8. 23266 75 72 3.85 9. 23266 75 73 3.76 10. 23266 75 74 3.80 11. 23266 75 75 3.84 12. 23266 75 76 3.94 13. 23266 75 77 3.95 14. 23266 75 78 3.81 15. 23266 75 79 3.82 16. 23266 75 80 ENDDATA 18 0 23266 75 81 ENDSUBENT 80 0 23266 7599999 SUBENT 23266076 20230215 231423266 76 1 BIB 8 22 23266 76 2 REACTION ((35-BR-81(N,G)35-BR-82,,RI,,AV)// 23266 76 3 (35-BR-81(N,G)35-BR-82,,SIG,,AV)) 23266 76 4 Q0 value (ratio of resonance integral to thermal 23266 76 5 neutron activation cross-section) 23266 76 6 SAMPLE - Provider - Alfa Aesar 23266 76 7 - Matrix - Liquid on paper 23266 76 8 Elemental content, % weight - 0.1 23266 76 9 Average sample thickness, mm - 1.5 23266 76 10 - Matrix - High purity KBrO(323266 76 11 Elemental content, % weight - 47.847 23266 76 12 Average sample thickness, mm - 0.15 23266 76 13 (35-BR-81,NAT=0.4931) 23266 76 14 METHOD Measurement at channels Y4 . 23266 76 15 DECAY-DATA (35-BR-82-G,35.30HR,DG,554.3,0.7110,DG,619.1,0.4350, 23266 76 16 DG,698.4,0.2830,DG,776.5,0.8340,DG,827.8,0.2400, 23266 76 17 DG,1044.0,0.2830,DG,1317.5,0.2680,DG,1474.9,0.1660) 23266 76 18 ANALYSIS The Q0 factor was determined by 23266 76 19 - the classical method. 23266 76 20 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 76 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 76 22 (DEP,23266077) Directly measured data . 23266 76 23 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 76 24 ENDBIB 22 0 23266 76 25 COMMON 2 3 23266 76 26 EN-MIN-NM EN-DN 23266 76 27 EV EV 23266 76 28 0.55 0.0253 23266 76 29 ENDCOMMON 3 0 23266 76 30 DATA 2 1 23266 76 31 DATA DATA-ERR 23266 76 32 NO-DIM PER-CENT 23266 76 33 19.3 1.5 23266 76 34 ENDDATA 3 0 23266 76 35 ENDSUBENT 34 0 23266 7699999 SUBENT 23266077 20141210 224123266 77 1 BIB 7 31 23266 77 2 REACTION ((35-BR-81(N,G)35-BR-82,,RI)// 23266 77 3 (35-BR-81(N,G)35-BR-82,,SIG)) 23266 77 4 Q0 value (ratio of resonance integral to thermal 23266 77 5 neutron activation cross-section) 23266 77 6 SAMPLE - Provider - Alfa Aesar 23266 77 7 - Matrix - Liquid on paper 23266 77 8 Elemental content, % weight - 0.1 23266 77 9 Average sample thickness, mm - 1.5 23266 77 10 - Matrix - High purity KBrO(323266 77 11 Elemental content, % weight - 47.847 23266 77 12 Average sample thickness, mm - 0.15 23266 77 13 (35-BR-81,NAT=0.4931) 23266 77 14 DECAY-DATA (35-BR-82-G,35.30HR,DG,554.3,0.7110,DG,619.1,0.4350, 23266 77 15 DG,698.4,0.2830,DG,776.5,0.8340,DG,827.8,0.2400, 23266 77 16 DG,1044.0,0.2830,DG,1317.5,0.2680,DG,1474.9,0.1660) 23266 77 17 METHOD Measurement at channel Y4. 23266 77 18 ANALYSIS The Q0 factor was determined by the classical method 23266 77 19 when inputting effective resonance energy factors 23266 77 20 from the literature. 23266 77 21 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 77 22 uncertainties ( 1 sigma) from: 23266 77 23 (ERR-1) alpha factor, 23266 77 24 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 77 25 epithermal flux for gold, 23266 77 26 (ERR-3) effective resonance energy Er, 23266 77 27 (ERR-4) Cd transmission factor FCd 23266 77 28 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 77 29 bare and Cd-covered sample. 23266 77 30 (ERR-S) Standard deviation. 23266 77 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 77 32 (COREL,23266076) Average data . 23266 77 33 ENDBIB 31 0 23266 77 34 COMMON 2 3 23266 77 35 EN-MIN-NM EN-DN 23266 77 36 EV EV 23266 77 37 0.55 0.0253 23266 77 38 ENDCOMMON 3 0 23266 77 39 DATA 8 1 23266 77 40 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 77 41 ERR-5 ERR-SYS 23266 77 42 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 77 43 PER-CENT PER-CENT 23266 77 44 19.3 1.0 1.0 1.1 0.1 0.65 23266 77 45 0.55 1.7 23266 77 46 ENDDATA 6 0 23266 77 47 ENDSUBENT 46 0 23266 7799999 SUBENT 23266078 20230215 231423266 78 1 BIB 5 11 23266 78 2 REACTION (35-BR-81(N,G)35-BR-82,,SIG,,AV) M+G 23266 78 3 SIG-0 - the average thermal neutron cross-section . 23266 78 4 for neutrons at an average energy of E0=25.3 meV 23266 78 5 or velocity v0=2200 m/s. 23266 78 6 ANALYSIS Derived from directly measured data. 23266 78 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 78 8 Uncertainty on exp. SIG-0 value comes from to the 23266 78 9 observed SD between gamma-lines. 23266 78 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 78 11 (DEP,23266079) Directly measured data. 23266 78 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 78 13 ENDBIB 11 0 23266 78 14 COMMON 1 3 23266 78 15 EN 23266 78 16 EV 23266 78 17 0.0253 23266 78 18 ENDCOMMON 3 0 23266 78 19 DATA 2 1 23266 78 20 DATA DATA-ERR 23266 78 21 B B 23266 78 22 2.59 0.03 23266 78 23 ENDDATA 3 0 23266 78 24 ENDSUBENT 23 0 23266 7899999 SUBENT 23266079 20141210 224123266 79 1 BIB 8 39 23266 79 2 REACTION (35-BR-81(N,G)35-BR-82,,SIG) M+G 23266 79 3 Directly measured thermal neutron cross-section SIG-0 23266 79 4 SAMPLE - Provider - Alfa Aesar 23266 79 5 - Matrix - Liquid on paper 23266 79 6 Elemental content, % weight - 0.1 23266 79 7 Average sample thickness, mm - 1.5 23266 79 8 - Matrix - High purity KBrO(323266 79 9 Elemental content, % weight - 47.847 23266 79 10 Average sample thickness, mm - 0.15 23266 79 11 (35-BR-81,NAT=0.4931) 23266 79 12 DECAY-DATA ((1.)35-BR-82-G,35.30HR,DG,554.3,0.7110) 23266 79 13 ((2.)35-BR-82-G,35.30HR,DG,619.1,0.4350) 23266 79 14 ((3.)35-BR-82-G,35.30HR,DG,698.4,0.2830) 23266 79 15 ((4.)35-BR-82-G,35.30HR,DG,776.5,0.8340) 23266 79 16 ((5.)35-BR-82-G,35.30HR,DG,827.8,0.2400) 23266 79 17 ((6.)35-BR-82-G,35.30HR,DG,1044.0,0.2830) 23266 79 18 ((7.)35-BR-82-G,35.30HR,DG,1317.5,0.2680) 23266 79 19 ((8.)35-BR-82-G,35.30HR,DG,1474.9,0.1660) 23266 79 20 (35-BR-82-M,6.13MIN) 23266 79 21 METHOD Measurement at channels Y4/Cavity, S84 . 23266 79 22 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 79 23 extrapolated with aid of the k0-definition, atomic 23266 79 24 weight, isotopic composition, the gamma intensities 23266 79 25 values. 23266 79 26 Defined according to their ADS(activation decay scheme,23266 79 27 including decay branching factors). 23266 79 28 ADD-RES Measured k0-values with one-sigma uncertainty 23266 79 29 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 79 30 554.3 2.39E-2 (+-0.9%) 23266 79 31 619.1 1.46E-2 (+-1.2%) 23266 79 32 698.4 9.44E-3 (+-0.8%) 23266 79 33 776.5 2.80E-2 (+-1.6%) 23266 79 34 827.8 8.03E-3 (+-1.6%) 23266 79 35 1044.0 9.19E-3 (+-1.0%) 23266 79 36 1317.5 9.04E-3 (+-1.2%) 23266 79 37 1474.9 5.52E-3 (+-1.8%) 23266 79 38 ERR-ANALYS Uncertainty is not given. 23266 79 39 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 79 40 (COREL,23266078) Average data 23266 79 41 ENDBIB 39 0 23266 79 42 COMMON 1 3 23266 79 43 EN 23266 79 44 EV 23266 79 45 0.0253 23266 79 46 ENDCOMMON 3 0 23266 79 47 DATA 2 8 23266 79 48 DATA DECAY-FLAG 23266 79 49 B NO-DIM 23266 79 50 2.60 1. 23266 79 51 2.60 2. 23266 79 52 2.59 3. 23266 79 53 2.60 4. 23266 79 54 2.60 5. 23266 79 55 2.52 6. 23266 79 56 2.61 7. 23266 79 57 2.58 8. 23266 79 58 ENDDATA 10 0 23266 79 59 ENDSUBENT 58 0 23266 7999999 SUBENT 23266080 20230215 231423266 80 1 BIB 8 18 23266 80 2 REACTION ((37-RB-85(N,G)37-RB-86,,RI,,AV)// 23266 80 3 (37-RB-85(N,G)37-RB-86,,SIG,,AV)) 23266 80 4 Q0 value (ratio of resonance integral to thermal 23266 80 5 neutron activation cross-section) 23266 80 6 SAMPLE - Provider - NIST 23266 80 7 - Matrix - Liquid on paper 23266 80 8 Elemental content, % weight - 1. 23266 80 9 Average sample thickness, mm - 1.5 23266 80 10 (37-RB-85,NAT=0.7217) 23266 80 11 METHOD Measurement at channels Y4 . 23266 80 12 DECAY-DATA (37-RB-86-G,18.63D,DG,1077.0,0.0864) 23266 80 13 (37-RB-86-M,1.02MIN) 23266 80 14 ANALYSIS The Q0 factor was determined by 23266 80 15 - the classical method. 23266 80 16 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 80 17 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 80 18 (DEP,23266081) Directly measured data . 23266 80 19 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 80 20 ENDBIB 18 0 23266 80 21 COMMON 2 3 23266 80 22 EN-MIN-NM EN-DN 23266 80 23 EV EV 23266 80 24 0.55 0.0253 23266 80 25 ENDCOMMON 3 0 23266 80 26 DATA 2 1 23266 80 27 DATA DATA-ERR 23266 80 28 NO-DIM PER-CENT 23266 80 29 14.4 1.5 23266 80 30 ENDDATA 3 0 23266 80 31 ENDSUBENT 30 0 23266 8099999 SUBENT 23266081 20141210 224123266 81 1 BIB 7 27 23266 81 2 REACTION ((37-RB-85(N,G)37-RB-86,,RI)// 23266 81 3 (37-RB-85(N,G)37-RB-86,,SIG)) 23266 81 4 Q0 value (ratio of resonance integral to thermal 23266 81 5 neutron activation cross-section) 23266 81 6 SAMPLE - Provider - NIST 23266 81 7 - Matrix - Liquid on paper 23266 81 8 Elemental content, % weight - 1. 23266 81 9 Average sample thickness, mm - 1.5 23266 81 10 (37-RB-85,NAT=0.7217) 23266 81 11 DECAY-DATA (37-RB-86-G,18.63D,DG,1077.0,0.0864) 23266 81 12 (37-RB-86-M,1.02MIN) 23266 81 13 METHOD Measurement at channel Y4. 23266 81 14 ANALYSIS The Q0 factor was determined by the classical method 23266 81 15 when inputting effective resonance energy factors 23266 81 16 from the literature. 23266 81 17 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 81 18 uncertainties ( 1 sigma) from: 23266 81 19 (ERR-1) alpha factor, 23266 81 20 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 81 21 epithermal flux for gold, 23266 81 22 (ERR-3) effective resonance energy Er, 23266 81 23 (ERR-4) Cd transmission factor FCd 23266 81 24 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 81 25 bare and Cd-covered sample. 23266 81 26 (ERR-S) Standard deviation. 23266 81 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 81 28 (COREL,23266080) Average data . 23266 81 29 ENDBIB 27 0 23266 81 30 COMMON 2 3 23266 81 31 EN-MIN-NM EN-DN 23266 81 32 EV EV 23266 81 33 0.55 0.0253 23266 81 34 ENDCOMMON 3 0 23266 81 35 DATA 8 1 23266 81 36 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 81 37 ERR-5 ERR-SYS 23266 81 38 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 81 39 PER-CENT PER-CENT 23266 81 40 14.4 1.0 1.0 0.9 0.1 0.65 23266 81 41 0.55 1.6 23266 81 42 ENDDATA 6 0 23266 81 43 ENDSUBENT 42 0 23266 8199999 SUBENT 23266082 20230215 231423266 82 1 BIB 5 11 23266 82 2 REACTION (37-RB-85(N,G)37-RB-86,,SIG,,AV) M+G 23266 82 3 SIG-0 - the average thermal neutron cross-section . 23266 82 4 for neutrons at an average energy of E0=25.3 meV 23266 82 5 or velocity v0=2200 m/s. 23266 82 6 ANALYSIS Derived from directly measured data. 23266 82 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 82 8 Uncertainty on exp. SIG-0 value comes from to the 23266 82 9 observed SD between gamma-lines. 23266 82 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 82 11 (DEP,23266083) Directly measured data. 23266 82 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 82 13 ENDBIB 11 0 23266 82 14 COMMON 1 3 23266 82 15 EN 23266 82 16 EV 23266 82 17 0.0253 23266 82 18 ENDCOMMON 3 0 23266 82 19 DATA 2 1 23266 82 20 DATA DATA-ERR 23266 82 21 B B 23266 82 22 0.521 0.005 23266 82 23 ENDDATA 3 0 23266 82 24 ENDSUBENT 23 0 23266 8299999 SUBENT 23266083 20141210 224123266 83 1 BIB 8 22 23266 83 2 REACTION (37-RB-85(N,G)37-RB-86,,SIG) 23266 83 3 Directly measured thermal neutron cross-section SIG-0 23266 83 4 SAMPLE - Provider - NIST 23266 83 5 - Matrix - Liquid on paper 23266 83 6 Elemental content, % weight - 1. 23266 83 7 Average sample thickness, mm - 1.5 23266 83 8 (37-RB-87,NAT=0.7217) 23266 83 9 DECAY-DATA ((1.)37-RB-86-G,18.63D,DG,1077.0,0.0864) reference line23266 83 10 (37-RB-86-M,1.02MIN) 23266 83 11 METHOD Measurement at channel Y4/Cavity . 23266 83 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 83 13 extrapolated with aid of the k0-definition, atomic 23266 83 14 weight, isotopic composition, the gamma intensities 23266 83 15 values. 23266 83 16 Defined according to their ADS(activation decay scheme,23266 83 17 including decay branching factors). 23266 83 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266 83 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 83 20 1077.0 7.94E-4 (+-0.7%) 23266 83 21 ERR-ANALYS Uncertainty is not given. 23266 83 22 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 83 23 (COREL,23266082) Average data 23266 83 24 ENDBIB 22 0 23266 83 25 COMMON 1 3 23266 83 26 EN 23266 83 27 EV 23266 83 28 0.0253 23266 83 29 ENDCOMMON 3 0 23266 83 30 DATA 2 1 23266 83 31 DATA DECAY-FLAG 23266 83 32 B NO-DIM 23266 83 33 0.521 1. 23266 83 34 ENDDATA 3 0 23266 83 35 ENDSUBENT 34 0 23266 8399999 SUBENT 23266084 20230215 231423266 84 1 BIB 8 18 23266 84 2 REACTION ((37-RB-87(N,G)37-RB-88,,RI,,AV)// 23266 84 3 (37-RB-87(N,G)37-RB-88,,SIG,,AV)) 23266 84 4 Q0 value (ratio of resonance integral to thermal 23266 84 5 neutron activation cross-section) 23266 84 6 SAMPLE - Provider - NIST 23266 84 7 - Matrix - Liquid on paper 23266 84 8 Elemental content, % weight - 1. 23266 84 9 Average sample thickness, mm - 1.5 23266 84 10 (37-RB-87,NAT=0.2783) 23266 84 11 METHOD Measurement at channel S84 . 23266 84 12 DECAY-DATA (37-RB-88,17.78MIN,DG,898.0,0.1468,DG,1382.5,0.00781, 23266 84 13 DG,1836.0,0.2273,DG,2677.9,0.02123) 23266 84 14 ANALYSIS The Q0 factor was determined by 23266 84 15 - the classical method. 23266 84 16 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 84 17 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 84 18 (DEP,23266085) Directly measured data . 23266 84 19 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 84 20 ENDBIB 18 0 23266 84 21 COMMON 2 3 23266 84 22 EN-MIN-NM EN-DN 23266 84 23 EV EV 23266 84 24 0.55 0.0253 23266 84 25 ENDCOMMON 3 0 23266 84 26 DATA 2 1 23266 84 27 DATA DATA-ERR 23266 84 28 NO-DIM PER-CENT 23266 84 29 25.9 2. 23266 84 30 ENDDATA 3 0 23266 84 31 ENDSUBENT 30 0 23266 8499999 SUBENT 23266085 20141210 224123266 85 1 BIB 7 27 23266 85 2 REACTION ((37-RB-87(N,G)37-RB-88,,RI)// 23266 85 3 (37-RB-87(N,G)37-RB-88,,SIG)) 23266 85 4 Q0 value (ratio of resonance integral to thermal 23266 85 5 neutron activation cross-section) 23266 85 6 SAMPLE - Provider - NIST 23266 85 7 - Matrix - Liquid on paper 23266 85 8 Elemental content, % weight - 1. 23266 85 9 Average sample thickness, mm - 1.5 23266 85 10 (37-RB-87,NAT=0.2783) 23266 85 11 DECAY-DATA (37-RB-88,17.78MIN,DG,898.0,0.1468,DG,1382.5,0.00781, 23266 85 12 DG,1836.0,0.2273,DG,2677.9,0.02123) 23266 85 13 METHOD Measurement at channel S84. 23266 85 14 ANALYSIS The Q0 factor was determined by the classical method 23266 85 15 when inputting effective resonance energy factors 23266 85 16 from the literature. 23266 85 17 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 85 18 uncertainties ( 1 sigma) from: 23266 85 19 (ERR-1) alpha factor, 23266 85 20 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 85 21 epithermal flux for gold, 23266 85 22 (ERR-3) effective resonance energy Er, 23266 85 23 (ERR-4) Cd transmission factor FCd 23266 85 24 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 85 25 bare and Cd-covered sample. 23266 85 26 (ERR-S) Standard deviation. 23266 85 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 85 28 (COREL,23266084) Average data . 23266 85 29 ENDBIB 27 0 23266 85 30 COMMON 2 3 23266 85 31 EN-MIN-NM EN-DN 23266 85 32 EV EV 23266 85 33 0.55 0.0253 23266 85 34 ENDCOMMON 3 0 23266 85 35 DATA 8 1 23266 85 36 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 85 37 ERR-5 ERR-SYS 23266 85 38 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 85 39 PER-CENT PER-CENT 23266 85 40 25.9 1.0 1.0 1.5 0.1 0.65 23266 85 41 0.55 2.0 23266 85 42 ENDDATA 6 0 23266 85 43 ENDSUBENT 42 0 23266 8599999 SUBENT 23266086 20230215 231423266 86 1 BIB 5 11 23266 86 2 REACTION (37-RB-87(N,G)37-RB-88,,SIG,,AV) 23266 86 3 SIG-0 - the average thermal neutron cross-section . 23266 86 4 for neutrons at an average energy of E0=25.3 meV 23266 86 5 or velocity v0=2200 m/s. 23266 86 6 ANALYSIS Derived from directly measured data. 23266 86 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 86 8 Uncertainty on exp. SIG-0 value comes from to the 23266 86 9 observed SD between gamma-lines. 23266 86 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 86 11 (DEP,23266087) Directly measured data. 23266 86 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 86 13 ENDBIB 11 0 23266 86 14 COMMON 1 3 23266 86 15 EN 23266 86 16 EV 23266 86 17 0.0253 23266 86 18 ENDCOMMON 3 0 23266 86 19 DATA 2 1 23266 86 20 DATA DATA-ERR 23266 86 21 B B 23266 86 22 0.094 0.003 23266 86 23 ENDDATA 3 0 23266 86 24 ENDSUBENT 23 0 23266 8699999 SUBENT 23266087 20141210 224123266 87 1 BIB 8 27 23266 87 2 REACTION (37-RB-87(N,G)37-RB-88,,SIG) 23266 87 3 Directly measured thermal neutron cross-section SIG-0 23266 87 4 SAMPLE - Provider - NIST 23266 87 5 - Matrix - Liquid on paper 23266 87 6 Elemental content, % weight - 1. 23266 87 7 Average sample thickness, mm - 1.5 23266 87 8 (37-RB-87,NAT=0.2783) 23266 87 9 DECAY-DATA ((1.)37-RB-88,17.78MIN,DG,898.0,0.1468) 23266 87 10 ((2.)37-RB-88,17.78MIN,DG,1382.5,0.00781) 23266 87 11 ((3.)37-RB-88,17.78MIN,DG,1836.0,0.2273) reference line23266 87 12 ((4.)37-RB-88,17.78MIN,DG,2677.9,0.02123) 23266 87 13 METHOD Measurement at channel S84 . 23266 87 14 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 87 15 extrapolated with aid of the k0-definition, atomic 23266 87 16 weight, isotopic composition, the gamma intensities 23266 87 17 values. 23266 87 18 Defined according to their ADS(activation decay scheme,23266 87 19 including decay branching factors). 23266 87 20 ADD-RES Measured k0-values with one-sigma uncertainty 23266 87 21 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 87 22 898.0 9.42E-5 (+-0.5%) 23266 87 23 1382.5 4.82E-6 (+-1.5%) 23266 87 24 1836.0 1.48E-4 (+-0.6%) 23266 87 25 2677.9 1.40E-5 (+-0.8%) 23266 87 26 ERR-ANALYS Uncertainty is not given. 23266 87 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 87 28 (COREL,23266086) Average data 23266 87 29 ENDBIB 27 0 23266 87 30 COMMON 1 3 23266 87 31 EN 23266 87 32 EV 23266 87 33 0.0253 23266 87 34 ENDCOMMON 3 0 23266 87 35 DATA 2 4 23266 87 36 DATA DECAY-FLAG 23266 87 37 B NO-DIM 23266 87 38 0.0943 1. 23266 87 39 0.0907 2. 23266 87 40 0.0957 3. 23266 87 41 0.0969 4. 23266 87 42 ENDDATA 6 0 23266 87 43 ENDSUBENT 42 0 23266 8799999 SUBENT 23266088 20230215 231423266 88 1 BIB 8 17 23266 88 2 REACTION ((39-Y-89(N,G)39-Y-90-M,,RI,,AV)// 23266 88 3 (39-Y-89(N,G)39-Y-90-M,,SIG,,AV)) 23266 88 4 Q0 value (ratio of resonance integral to thermal 23266 88 5 neutron activation cross-section) 23266 88 6 SAMPLE - Provider - Dr.Hult 23266 88 7 - Matrix - Foil 23266 88 8 Elemental content, % weight - 99.3 23266 88 9 Average sample thickness, mm - 0.1 23266 88 10 (39-Y-89,NAT=1.00) 23266 88 11 METHOD Measurement at channel S84 . 23266 88 12 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.5,0.9730,DG,479.5,0.9074) 23266 88 13 ANALYSIS The Q0 factor was determined by 23266 88 14 - the classical method. 23266 88 15 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 88 16 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 88 17 (DEP,23266089) Directly measured data . 23266 88 18 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 88 19 ENDBIB 17 0 23266 88 20 COMMON 2 3 23266 88 21 EN-MIN-NM EN-DN 23266 88 22 EV EV 23266 88 23 0.55 0.0253 23266 88 24 ENDCOMMON 3 0 23266 88 25 DATA 2 1 23266 88 26 DATA DATA-ERR 23266 88 27 NO-DIM PER-CENT 23266 88 28 4.08 1.5 23266 88 29 ENDDATA 3 0 23266 88 30 ENDSUBENT 29 0 23266 8899999 SUBENT 23266089 20141210 224123266 89 1 BIB 7 26 23266 89 2 REACTION ((39-Y-89(N,G)39-Y-90-M,,RI)// 23266 89 3 (39-Y-89(N,G)39-Y-90-M,,SIG)) 23266 89 4 Q0 value (ratio of resonance integral to thermal 23266 89 5 neutron activation cross-section) 23266 89 6 SAMPLE - Provider - Dr.Hult 23266 89 7 - Matrix - Foil 23266 89 8 Elemental content, % weight - 99.3 23266 89 9 Average sample thickness, mm - 0.1 23266 89 10 (39-Y-89,NAT=1.00) 23266 89 11 METHOD Measurement at channel S84 . 23266 89 12 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.5,0.9730,DG,479.5,0.9074) 23266 89 13 ANALYSIS The Q0 factor was determined by the classical method 23266 89 14 when inputting effective resonance energy factors 23266 89 15 from the literature. 23266 89 16 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 89 17 uncertainties ( 1 sigma) from: 23266 89 18 (ERR-1) alpha factor, 23266 89 19 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 89 20 epithermal flux for gold, 23266 89 21 (ERR-3) effective resonance energy Er, 23266 89 22 (ERR-4) Cd transmission factor FCd 23266 89 23 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 89 24 bare and Cd-covered sample. 23266 89 25 (ERR-S) Standard deviation. 23266 89 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 89 27 (COREL,23266088) Average data . 23266 89 28 ENDBIB 26 0 23266 89 29 COMMON 2 3 23266 89 30 EN-MIN-NM EN-DN 23266 89 31 EV EV 23266 89 32 0.55 0.0253 23266 89 33 ENDCOMMON 3 0 23266 89 34 DATA 8 1 23266 89 35 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 89 36 ERR-5 ERR-SYS 23266 89 37 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 89 38 PER-CENT PER-CENT 23266 89 39 4.08 1.5 1.0 1.0 0.15 0.6 23266 89 40 0.55 1.65 23266 89 41 ENDDATA 6 0 23266 89 42 ENDSUBENT 41 0 23266 8999999 SUBENT 23266090 20230215 231423266 90 1 BIB 6 12 23266 90 2 REACTION (39-Y-89(N,G)39-Y-90-M,,SIG,,AV) 23266 90 3 SIG-0 - the average thermal neutron cross-section . 23266 90 4 for neutrons at an average energy of E0=25.3 meV 23266 90 5 or velocity v0=2200 m/s. 23266 90 6 DECAY-DATA (39-Y-90-M,3.19HR) 23266 90 7 ANALYSIS Derived from directly measured data. 23266 90 8 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 90 9 Uncertainty on exp. SIG-0 value comes from to the 23266 90 10 observed SD between gamma-lines. 23266 90 11 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 90 12 (DEP,23266091) Directly measured data. 23266 90 13 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 90 14 ENDBIB 12 0 23266 90 15 COMMON 1 3 23266 90 16 EN 23266 90 17 EV 23266 90 18 0.0253 23266 90 19 ENDCOMMON 3 0 23266 90 20 DATA 2 1 23266 90 21 DATA DATA-ERR 23266 90 22 B B 23266 90 23 0.00107 0.00001 23266 90 24 ENDDATA 3 0 23266 90 25 ENDSUBENT 24 0 23266 9099999 SUBENT 23266091 20141210 224123266 91 1 BIB 8 23 23266 91 2 REACTION (39-Y-89(N,G)39-Y-90-M,,SIG) 23266 91 3 Directly measured thermal neutron cross-section SIG-0 23266 91 4 SAMPLE - Provider - Dr.Hult 23266 91 5 - Matrix - Foil 23266 91 6 Elemental content, % weight - 99.3 23266 91 7 Average sample thickness, mm - 0.1 23266 91 8 (39-Y-89,NAT=1.00) 23266 91 9 DECAY-DATA ((1.)39-Y-90-M,3.19HR,DG,202.5,0.9730) 23266 91 10 ((2.)39-Y-90-M,3.19HR,DG,479.5,0.9074) 23266 91 11 METHOD Measurement at channel S84 . 23266 91 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 91 13 extrapolated with aid of the k0-definition, atomic 23266 91 14 weight, isotopic composition, the gamma intensities 23266 91 15 values. 23266 91 16 Defined according to their ADS(activation decay scheme,23266 91 17 including decay branching factors). 23266 91 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266 91 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 91 20 202.5 2.45E-5 (+-0.5%) 23266 91 21 479.5 2.26E-5 (+-0.5%) 23266 91 22 ERR-ANALYS Uncertainty is not given. 23266 91 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 91 24 (COREL,23266090) Average data 23266 91 25 ENDBIB 23 0 23266 91 26 COMMON 1 3 23266 91 27 EN 23266 91 28 EV 23266 91 29 0.0253 23266 91 30 ENDCOMMON 3 0 23266 91 31 DATA 2 2 23266 91 32 DATA DECAY-FLAG 23266 91 33 B NO-DIM 23266 91 34 0.00107 1. 23266 91 35 0.00106 2. 23266 91 36 ENDDATA 4 0 23266 91 37 ENDSUBENT 36 0 23266 9199999 SUBENT 23266092 20230215 231423266 92 1 BIB 9 29 23266 92 2 REACTION 1((40-ZR-94(N,G)40-ZR-95,,RI,,AV)// 23266 92 3 (40-ZR-94(N,G)40-ZR-95,,SIG,,AV)) 23266 92 4 2((40-ZR-94(N,G)40-ZR-95,,RI)// 23266 92 5 (40-ZR-94(N,G)40-ZR-95,,SIG)) 23266 92 6 Q0 value (ratio of resonance integral to thermal 23266 92 7 neutron activation cross-section) 23266 92 8 SAMPLE - Provider - Alfa Aesar 23266 92 9 Matrix - Foil 23266 92 10 Elemental content, % weight - 99.8 23266 92 11 Average sample thickness, mm - 0.127 23266 92 12 (40-ZR-94,NAT=0.1738) 23266 92 13 METHOD Measurement at channels S84, Y4, X26 . 23266 92 14 DECAY-DATA (40-ZR-95,64.03D,DG,724.2,0.44270,DG,756.7,0.54380) 23266 92 15 64.03+-0.06 d 23266 92 16 (41-NB-95-G,34.99D,DG,765.8,0.99808) 34.99+-0.03 d 23266 92 17 (41-NB-95-M,3.61D) 3.61+-0.03 d 23266 92 18 ANALYSIS The Q0 factor was determined by 23266 92 19 1- the classical method: through the weighted mean and 23266 92 20 observed standard deviation of the 3 irradiation 23266 92 21 channels employed (Y4, S84, X26), when inputting Er 23266 92 22 factors from the literature. 23266 92 23 2- the a-vector method: through the parameters 23266 92 24 (m, b) --> determination of the value as well. 23266 92 25 ADD-RES Effective resonance Energy was defined by a-vect23266 92 26 method to be 6261.eV ( +-9%, 2sigma). 23266 92 27 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 92 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 92 29 1(DEP,23266093) Directly measured data . 23266 92 30 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 92 31 ENDBIB 29 0 23266 92 32 COMMON 2 3 23266 92 33 EN-MIN-NM EN-DN 23266 92 34 EV EV 23266 92 35 0.55 0.0253 23266 92 36 ENDCOMMON 3 0 23266 92 37 DATA 4 1 23266 92 38 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266 92 39 NO-DIM PER-CENT NO-DIM PER-CENT 23266 92 40 5.02 0.5 5.02 2.5 23266 92 41 ENDDATA 3 0 23266 92 42 ENDSUBENT 41 0 23266 9299999 SUBENT 23266093 20141210 224123266 93 1 BIB 7 32 23266 93 2 REACTION ((40-ZR-94(N,G)40-ZR-95,,RI)// 23266 93 3 (40-ZR-94(N,G)40-ZR-95,,SIG)) 23266 93 4 Q0 value (ratio of resonance integral to thermal 23266 93 5 neutron activation cross-section) 23266 93 6 SAMPLE - Provider - Alfa Aesar 23266 93 7 Matrix - Foil 23266 93 8 Elemental content, % weight - 99.8 23266 93 9 Average sample thickness, mm - 0.127 23266 93 10 (40-ZR-94,NAT=0.1738) 23266 93 11 DECAY-DATA (40-ZR-95,64.03D,DG,724.2,0.44270,DG,756.7,0.54380) 23266 93 12 64.03+-0.06 d 23266 93 13 (41-NB-95-G,34.99D,DG,765.8,0.99808) 34.99+-0.03 d 23266 93 14 (41-NB-95-M,3.61D) 3.61+-0.03 d 23266 93 15 FLAG Measurement at channels 23266 93 16 (1.) S84, 23266 93 17 (2.) Y4 23266 93 18 (3.) X26 23266 93 19 ANALYSIS The Q0 factor was determined by the classical method 23266 93 20 when inputting effective resonance energy factors 23266 93 21 from the literature. 23266 93 22 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 93 23 uncertainties ( 1 sigma) from: 23266 93 24 (ERR-1) alpha factor, 23266 93 25 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 93 26 epithermal flux for gold, 23266 93 27 (ERR-3) effective resonance energy Er, 23266 93 28 (ERR-4) Cd transmission factor FCd 23266 93 29 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 93 30 bare and Cd-covered sample. 23266 93 31 (ERR-S) Standard deviation. 23266 93 32 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 93 33 (COREL,23266092) Average data . 23266 93 34 ENDBIB 32 0 23266 93 35 COMMON 2 3 23266 93 36 EN-MIN-NM EN-DN 23266 93 37 EV EV 23266 93 38 0.55 0.0253 23266 93 39 ENDCOMMON 3 0 23266 93 40 DATA 9 3 23266 93 41 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 93 42 ERR-5 ERR-SYS FLAG 23266 93 43 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 93 44 PER-CENT PER-CENT NO-DIM 23266 93 45 4.98 1.25 2.05 1.5 0.25 0.75 23266 93 46 0.8 2.8 1. 23266 93 47 5.06 0.9 1.7 1.35 0.4 0.6 23266 93 48 0.7 2.4 2. 23266 93 49 4.99 1.65 2.0 1.35 0.8 0.55 23266 93 50 0.6 2.65 3. 23266 93 51 ENDDATA 10 0 23266 93 52 ENDSUBENT 51 0 23266 9399999 SUBENT 23266094 20230215 231423266 94 1 BIB 5 11 23266 94 2 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG,,AV) 23266 94 3 SIG-0 - the average thermal neutron cross-section . 23266 94 4 for neutrons at an average energy of E0=25.3 meV 23266 94 5 or velocity v0=2200 m/s. 23266 94 6 ANALYSIS Derived from directly measured data. 23266 94 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 94 8 Uncertainty on exp. SIG-0 value comes from to the 23266 94 9 observed SD between gamma-lines. 23266 94 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 94 11 (DEP,23266095) Directly measured data. 23266 94 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 94 13 ENDBIB 11 0 23266 94 14 COMMON 1 3 23266 94 15 EN 23266 94 16 EV 23266 94 17 0.0253 23266 94 18 ENDCOMMON 3 0 23266 94 19 DATA 2 1 23266 94 20 DATA DATA-ERR 23266 94 21 B B 23266 94 22 0.0517 0.0003 23266 94 23 ENDDATA 3 0 23266 94 24 ENDSUBENT 23 0 23266 9499999 SUBENT 23266095 20141210 224123266 95 1 BIB 9 38 23266 95 2 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG) 23266 95 3 Directly measured thermal neutron cross-section SIG-0 23266 95 4 SAMPLE - Provider - Alfa Aesar 23266 95 5 Matrix - Foil 23266 95 6 Elemental content, % weight - 99.8 23266 95 7 Average sample thickness, mm - 0.127 23266 95 8 (40-ZR-94,NAT=0.1738) 23266 95 9 DECAY-DATA ((1.)40-ZR-95,64.03D,DG,724.2,0.44270) 23266 95 10 ((2.)40-ZR-95,64.03D,DG,756.7,0.54380) 23266 95 11 64.03+-0.06 d 23266 95 12 ((3.)41-NB-95-G,34.99D,DG,765.8,0.99808) 34.99+-0.03 d 23266 95 13 (41-NB-95-M,3.61D) 3.61+-0.03 d 23266 95 14 REL-REF (A,,F.De Corte,T,DECORTE,1987) 23266 95 15 The k0-standardization method: a move to the 23266 95 16 optimization of neutron activation analysis. 23266 95 17 Aggregate Thesis, Gent University, Belgium ( old 23266 95 18 measurement, 765.8 keV gamma was used). 23266 95 19 Value of c-s 0.0495 b - on base of old ADS. 23266 95 20 New data for ADS from: 23266 95 21 CEA - Laboratoire National Henri Becquerel (2012) 23266 95 22 Recommended Data. 23266 95 23 http://www.nucleide.org/DDEP WG/DDEPdata.htm. 23266 95 24 Accessed 2 Feb 2012. 23266 95 25 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266 95 26 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 95 27 extrapolated with aid of the k0-definition, atomic 23266 95 28 weight, isotopic composition, the gamma intensities 23266 95 29 values. 23266 95 30 Defined according to their ADS(activation decay scheme,23266 95 31 including decay branching factors). 23266 95 32 ADD-RES Measured k0-values with one-sigma uncertainty 23266 95 33 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 95 34 724.2 9.08E-5 (+-0.5%) 23266 95 35 756.7 1.13E-4 (+-0.5%) 23266 95 36 765.8 2.24E-6 (+-0.4%) 23266 95 37 ERR-ANALYS Uncertainty is not given. 23266 95 38 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 95 39 (COREL,23266094) Average data 23266 95 40 ENDBIB 38 0 23266 95 41 COMMON 1 3 23266 95 42 EN 23266 95 43 EV 23266 95 44 0.0253 23266 95 45 ENDCOMMON 3 0 23266 95 46 DATA 2 3 23266 95 47 DATA DECAY-FLAG 23266 95 48 B NO-DIM 23266 95 49 0.0515 1. 23266 95 50 0.0520 2. 23266 95 51 0.0515 3. 23266 95 52 ENDDATA 5 0 23266 95 53 ENDSUBENT 52 0 23266 9599999 SUBENT 23266096 20230215 231423266 96 1 BIB 8 21 23266 96 2 REACTION ((41-NB-93(N,G)41-NB-94-M,,RI,,AV)// 23266 96 3 (41-NB-93(N,G)41-NB-94-M,,SIG,,AV)) 23266 96 4 Q0 value (ratio of resonance integral to thermal 23266 96 5 neutron activation cross-section) 23266 96 6 SAMPLE - Provider - IRMM 23266 96 7 - Matrix - Foil,Al alloy 23266 96 8 Elemental content, % weight - 10. 23266 96 9 Average sample thickness, mm - 0.1 23266 96 10 - Provider - CBNM 23266 96 11 - Matrix - Foil 23266 96 12 Elemental content, % weight - >99.99 23266 96 13 Average sample thickness, mm - 0.022; 0.0762 23266 96 14 (41-NB-93,NAT=1.00) 23266 96 15 METHOD Measurement at channel S84 . 23266 96 16 DECAY-DATA (41-NB-94-M,6.26MIN,DG,871.0,0.0050) 23266 96 17 ANALYSIS The Q0 factor was determined by 23266 96 18 - the classical method. 23266 96 19 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 96 20 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 96 21 (DEP,23266097) Directly measured data . 23266 96 22 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 96 23 ENDBIB 21 0 23266 96 24 COMMON 2 3 23266 96 25 EN-MIN-NM EN-DN 23266 96 26 EV EV 23266 96 27 0.55 0.0253 23266 96 28 ENDCOMMON 3 0 23266 96 29 DATA 2 1 23266 96 30 DATA DATA-ERR 23266 96 31 NO-DIM PER-CENT 23266 96 32 7.28 1.5 23266 96 33 ENDDATA 3 0 23266 96 34 ENDSUBENT 33 0 23266 9699999 SUBENT 23266097 20141210 224123266 97 1 BIB 7 30 23266 97 2 REACTION ((41-NB-93(N,G)41-NB-94-M,,RI)// 23266 97 3 (41-NB-93(N,G)41-NB-94-M,,SIG)) 23266 97 4 Q0 value (ratio of resonance integral to thermal 23266 97 5 neutron activation cross-section) 23266 97 6 SAMPLE - Provider - IRMM 23266 97 7 - Matrix - Foil,Al alloy 23266 97 8 Elemental content, % weight - 10. 23266 97 9 Average sample thickness, mm - 0.1 23266 97 10 - Provider - CBNM 23266 97 11 - Matrix - Foil 23266 97 12 Elemental content, % weight - >99.99 23266 97 13 Average sample thickness, mm - 0.022; 0.0762 23266 97 14 (41-NB-93,NAT=1.00) 23266 97 15 METHOD Measurement at channel S84 . 23266 97 16 DECAY-DATA (41-NB-94-M,6.26MIN,DG,871.0,0.0050) 23266 97 17 ANALYSIS The Q0 factor was determined by the classical method 23266 97 18 when inputting effective resonance energy factors 23266 97 19 from the literature. 23266 97 20 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266 97 21 uncertainties ( 1 sigma) from: 23266 97 22 (ERR-1) alpha factor, 23266 97 23 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266 97 24 epithermal flux for gold, 23266 97 25 (ERR-3) effective resonance energy Er, 23266 97 26 (ERR-4) Cd transmission factor FCd 23266 97 27 (ERR-5) A/ACd -ratio of induced gamma activities, 23266 97 28 bare and Cd-covered sample. 23266 97 29 (ERR-S) Standard deviation. 23266 97 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266 97 31 (COREL,23266096) Average data . 23266 97 32 ENDBIB 30 0 23266 97 33 COMMON 2 3 23266 97 34 EN-MIN-NM EN-DN 23266 97 35 EV EV 23266 97 36 0.55 0.0253 23266 97 37 ENDCOMMON 3 0 23266 97 38 DATA 8 1 23266 97 39 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266 97 40 ERR-5 ERR-SYS 23266 97 41 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266 97 42 PER-CENT PER-CENT 23266 97 43 7.28 2.0 1.05 1.0 0.1 0.55 23266 97 44 0.55 1.65 23266 97 45 ENDDATA 6 0 23266 97 46 ENDSUBENT 45 0 23266 9799999 SUBENT 23266098 20230215 231423266 98 1 BIB 5 11 23266 98 2 REACTION (41-NB-93(N,G)41-NB-94-M,,SIG,,AV) 23266 98 3 SIG-0 - the average thermal neutron cross-section . 23266 98 4 for neutrons at an average energy of E0=25.3 meV 23266 98 5 or velocity v0=2200 m/s. 23266 98 6 ANALYSIS Derived from directly measured data. 23266 98 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266 98 8 Uncertainty on exp. SIG-0 value comes from to the 23266 98 9 observed SD between gamma-lines. 23266 98 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 98 11 (DEP,23266099) Directly measured data. 23266 98 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266 98 13 ENDBIB 11 0 23266 98 14 COMMON 1 3 23266 98 15 EN 23266 98 16 EV 23266 98 17 0.0253 23266 98 18 ENDCOMMON 3 0 23266 98 19 DATA 2 1 23266 98 20 DATA DATA-ERR 23266 98 21 B B 23266 98 22 0.853 0.008 23266 98 23 ENDDATA 3 0 23266 98 24 ENDSUBENT 23 0 23266 9899999 SUBENT 23266099 20141210 224123266 99 1 BIB 8 25 23266 99 2 REACTION (41-NB-93(N,G)41-NB-94-M,,SIG) 23266 99 3 Directly measured thermal neutron cross-section SIG-0 23266 99 4 SAMPLE - Provider - IRMM 23266 99 5 - Matrix - Foil,Al alloy 23266 99 6 Elemental content, % weight - 10. 23266 99 7 Average sample thickness, mm - 0.1 23266 99 8 - Provider - CBNM 23266 99 9 - Matrix - Foil 23266 99 10 Elemental content, % weight - >99.99 23266 99 11 Average sample thickness, mm - 0.022; 0.0762 23266 99 12 (41-NB-93,NAT=1.00) 23266 99 13 DECAY-DATA (41-NB-94-M,6.26MIN,DG,871.0,0.0050) reference line 23266 99 14 METHOD Measurement at channel S84 . 23266 99 15 ANALYSIS An thermal neutron cross-section SIG-0 was 23266 99 16 extrapolated with aid of the k0-definition, atomic 23266 99 17 weight, isotopic composition, the gamma intensities 23266 99 18 values. 23266 99 19 Defined according to their ADS(activation decay scheme,23266 99 20 including decay branching factors). 23266 99 21 ADD-RES Measured k0-values with one-sigma uncertainty 23266 99 22 E-gamma,keV k0, no-dim.(uncertainty,%) 23266 99 23 871.0 9.59E-5 (+-0.4%) 23266 99 24 ERR-ANALYS Uncertainty is not given. 23266 99 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266 99 26 (COREL,23266098) Average data 23266 99 27 ENDBIB 25 0 23266 99 28 COMMON 1 3 23266 99 29 EN 23266 99 30 EV 23266 99 31 0.0253 23266 99 32 ENDCOMMON 3 0 23266 99 33 DATA 1 1 23266 99 34 DATA 23266 99 35 B 23266 99 36 0.853 23266 99 37 ENDDATA 3 0 23266 99 38 ENDSUBENT 37 0 23266 9999999 SUBENT 23266100 20230215 231423266100 1 BIB 9 28 23266100 2 REACTION 1((42-MO-98(N,G)42-MO-99,,RI,,AV)// 23266100 3 (42-MO-98(N,G)42-MO-99,,SIG,,AV)) 23266100 4 2((42-MO-98(N,G)42-MO-99,,RI)// 23266100 5 (42-MO-98(N,G)42-MO-99,,SIG)) 23266100 6 Q0 value (ratio of resonance integral to thermal 23266100 7 neutron activation cross-section) 23266100 8 SAMPLE - Provider - Goodfellow 23266100 9 Matrix - Foil 23266100 10 Elemental content, % weight - 99.9 23266100 11 Average sample thickness, mm - 0.025 23266100 12 (42-MO-98,NAT=0.2439) 24.39+-0.37 % 23266100 13 METHOD Measurement at channels S84, Y4, X26 . 23266100 14 DECAY-DATA (42-MO-99,2.748D,DG,181.0,0.0601,DG,366.4,0.119, 23266100 15 DG,739.0,0.1212,DG,777.0,0.0428) 23266100 16 (43-TC-99-M,6.01HR,DG,140.5,0.885) 23266100 17 ANALYSIS The Q0 factor was determined by 23266100 18 1- the classical method: through the weighted mean and 23266100 19 observed standard deviation of the 3 irradiation 23266100 20 channels employed (Y4, S84, X26), when inputting Er 23266100 21 factors from the literature. 23266100 22 2- the a-vector method: through the parameters 23266100 23 (m, b) --> determination of the value as well. 23266100 24 ADD-RES Effective resonance Energy was defined by a-vect23266100 25 method to be 262.eV ( +-9%, 2sigma). 23266100 26 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266100 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266100 28 1(DEP,23266101) Directly measured data . 23266100 29 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266100 30 ENDBIB 28 0 23266100 31 COMMON 2 3 23266100 32 EN-MIN-NM EN-DN 23266100 33 EV EV 23266100 34 0.55 0.0253 23266100 35 ENDCOMMON 3 0 23266100 36 DATA 4 1 23266100 37 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266100 38 NO-DIM PER-CENT NO-DIM PER-CENT 23266100 39 54.0 4. 54.8 3. 23266100 40 ENDDATA 3 0 23266100 41 ENDSUBENT 40 0 2326610099999 SUBENT 23266101 20180202 226823266101 1 BIB 8 34 23266101 2 REACTION ((42-MO-98(N,G)42-MO-99,,RI)// 23266101 3 (42-MO-98(N,G)42-MO-99,,SIG)) 23266101 4 Q0 value (ratio of resonance integral to thermal 23266101 5 neutron activation cross-section) 23266101 6 SAMPLE - Provider - Goodfellow 23266101 7 Matrix - Foil 23266101 8 Elemental content, % weight - 99.9 23266101 9 Average sample thickness, mm - 0.025 23266101 10 (42-MO-98,NAT=0.2439) 24.39+-0.37 % 23266101 11 DECAY-DATA (42-MO-99,2.748D,DG,181.0,0.0601, 23266101 12 DG,366.4,0.119, 23266101 13 DG,739.0,0.1212, 23266101 14 DG,777.0,0.0428) 23266101 15 (43-TC-99-M,6.01HR,DG,140.5,0.885) 23266101 16 FLAG Measurement at channels 23266101 17 (1.) S84, 23266101 18 (2.) Y4, 23266101 19 (3.) X26 23266101 20 ANALYSIS The Q0 factor was determined by the classical method 23266101 21 when inputting effective resonance energy factors 23266101 22 from the literature. 23266101 23 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266101 24 uncertainties ( 1 sigma) from: 23266101 25 (ERR-1) alpha factor, 23266101 26 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266101 27 epithermal flux for gold, 23266101 28 (ERR-3) effective resonance energy Er, 23266101 29 (ERR-4) Cd transmission factor FCd 23266101 30 (ERR-5) A/ACd -ratio of induced gamma activities, 23266101 31 bare and Cd-covered sample. 23266101 32 (ERR-S) Standard deviation. 23266101 33 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266101 34 (COREL,23266100) Average data . 23266101 35 HISTORY (20180202A) M.M. DATA misprint was corrected 23266101 36 ENDBIB 34 0 23266101 37 COMMON 2 3 23266101 38 EN-MIN-NM EN-DN 23266101 39 EV EV 23266101 40 0.55 0.0253 23266101 41 ENDCOMMON 3 0 23266101 42 DATA 9 3 23266101 43 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266101 44 ERR-5 ERR-SYS FLAG 23266101 45 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266101 46 PER-CENT PER-CENT NO-DIM 23266101 47 54.5 2.9 2.0 1.75 0.25 0.85 23266101 48 1.3 3.1 1. 23266101 49 56.0 1.05 1.3 1.65 0.45 0.65 23266101 50 1.1 2.5 2. 23266101 51 50.9 0.55 1.9 1.55 0.65 0.7 23266101 52 1.05 2.85 3. 23266101 53 ENDDATA 10 0 23266101 54 ENDSUBENT 53 0 2326610199999 SUBENT 23266102 20230215 231423266102 1 BIB 5 11 23266102 2 REACTION (42-MO-98(N,G)42-MO-99,,SIG,,AV) 23266102 3 SIG-0 - the average thermal neutron cross-section . 23266102 4 for neutrons at an average energy of E0=25.3 meV 23266102 5 or velocity v0=2200 m/s. 23266102 6 ANALYSIS Derived from directly measured data. 23266102 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266102 8 Uncertainty on exp. SIG-0 value comes from to the 23266102 9 observed SD between gamma-lines. 23266102 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266102 11 (DEP,23266103) Directly measured data. 23266102 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266102 13 ENDBIB 11 0 23266102 14 COMMON 1 3 23266102 15 EN 23266102 16 EV 23266102 17 0.0253 23266102 18 ENDCOMMON 3 0 23266102 19 DATA 2 1 23266102 20 DATA DATA-ERR 23266102 21 B B 23266102 22 0.128 0.002 23266102 23 ENDDATA 3 0 23266102 24 ENDSUBENT 23 0 2326610299999 SUBENT 23266103 20141210 224123266103 1 BIB 8 29 23266103 2 REACTION (42-MO-98(N,G)42-MO-99,,SIG) 23266103 3 Directly measured thermal neutron cross-section SIG-0 23266103 4 SAMPLE - Provider - Goodfellow 23266103 5 Matrix - Foil 23266103 6 Elemental content, % weight - 99.9 23266103 7 Average sample thickness, mm - 0.025 23266103 8 (42-MO-98,NAT=0.2439) 24.39+-0.37 % 23266103 9 DECAY-DATA ((1.)42-MO-99,2.748D,DG,181.0,0.0601) 23266103 10 ((2.)42-MO-99,2.748D,DG,366.4,0.119) 23266103 11 ((3.)42-MO-99,2.748D,DG,739.0,0.1212) reference line 23266103 12 ((4.)42-MO-99,2.748D,DG,777.0,0.0428) 23266103 13 ((5.)43-TC-99-M,6.01HR,DG,140.5,0.885) 23266103 14 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266103 15 ANALYSIS An thermal neutron cross-section SIG-0 was 23266103 16 extrapolated with aid of the k0-definition, atomic 23266103 17 weight, isotopic composition, the gamma intensities 23266103 18 values. 23266103 19 Defined according to their ADS(activation decay scheme,23266103 20 including decay branching factors). 23266103 21 ADD-RES Measured k0-values with one-sigma uncertainty 23266103 22 E-gamma,keV k0, no-dim.(uncertainty,%) 23266103 23 181.0 4.16E-5 (+-0.8%) 23266103 24 366.4 8.07E-6 (+-0.5%) 23266103 25 739.0 8.20E-6 (+-0.9%) 23266103 26 777.0 2.86E-5 (+-0.1%) 23266103 27 140.5 5.29E-4 (+-0.2%) 23266103 28 ERR-ANALYS Uncertainty is not given. 23266103 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266103 30 (COREL,23266102) Average data 23266103 31 ENDBIB 29 0 23266103 32 COMMON 1 3 23266103 33 EN 23266103 34 EV 23266103 35 0.0253 23266103 36 ENDCOMMON 3 0 23266103 37 DATA 2 5 23266103 38 DATA DECAY-FLAG 23266103 39 B NO-DIM 23266103 40 0.130 1. 23266103 41 0.127 2. 23266103 42 0.127 3. 23266103 43 0.126 4. 23266103 44 0.128 5. 23266103 45 ENDDATA 7 0 23266103 46 ENDSUBENT 45 0 2326610399999 SUBENT 23266104 20230215 231423266104 1 BIB 8 22 23266104 2 REACTION ((47-AG-107(N,G)47-AG-108,,RI,,AV)// 23266104 3 (47-AG-107(N,G)47-AG-108,,SIG,,AV)) 23266104 4 Q0 value (ratio of resonance integral to thermal 23266104 5 neutron activation cross-section) 23266104 6 SAMPLE - Provider - IRMM 23266104 7 - Matrix - Foil,Al alloy 23266104 8 Elemental content, % weight - 1. 23266104 9 Average sample thickness, mm - 0.1 23266104 10 - Provider - Goodfellow 23266104 11 - Matrix - Wire 23266104 12 Elemental content, % weight - 99.9 23266104 13 Average sample thickness, mm - 1. 23266104 14 (47-AG-107,NAT=0.51839) 51.839+-0.008 % 23266104 15 DECAY-DATA (47-AG-108-G,2.37MIN,DG,434.0,0.0050,DG,618.9,0.0026, 23266104 16 DG,633.0,0.0174) 23266104 17 METHOD Measurement at channel S84 . 23266104 18 ANALYSIS The Q0 factor was determined by 23266104 19 - the classical method. 23266104 20 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266104 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266104 22 (DEP,23266105) Directly measured data . 23266104 23 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266104 24 ENDBIB 22 0 23266104 25 COMMON 2 3 23266104 26 EN-MIN-NM EN-DN 23266104 27 EV EV 23266104 28 0.55 0.0253 23266104 29 ENDCOMMON 3 0 23266104 30 DATA 2 1 23266104 31 DATA DATA-ERR 23266104 32 NO-DIM PER-CENT 23266104 33 2.72 1.5 23266104 34 ENDDATA 3 0 23266104 35 ENDSUBENT 34 0 2326610499999 SUBENT 23266105 20141210 224123266105 1 BIB 7 31 23266105 2 REACTION ((47-AG-107(N,G)47-AG-108,,RI)// 23266105 3 (47-AG-107(N,G)47-AG-108,,SIG)) 23266105 4 Q0 value (ratio of resonance integral to thermal 23266105 5 neutron activation cross-section) 23266105 6 SAMPLE - Provider - IRMM 23266105 7 - Matrix - Foil,Al alloy 23266105 8 Elemental content, % weight - 1. 23266105 9 Average sample thickness, mm - 0.1 23266105 10 - Provider - Goodfellow 23266105 11 - Matrix - Wire 23266105 12 Elemental content, % weight - 99.9 23266105 13 Average sample thickness, mm - 1. 23266105 14 (47-AG-107,NAT=0.51839) 51.839+-0.008 % 23266105 15 DECAY-DATA (47-AG-108-G,2.37MIN,DG,434.0,0.0050,DG,618.9,0.0026, 23266105 16 DG,633.0,0.0174) 23266105 17 METHOD Measurement at channel S84 . 23266105 18 ANALYSIS The Q0 factor was determined by the classical method 23266105 19 when inputting effective resonance energy factors 23266105 20 from the literature. 23266105 21 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266105 22 uncertainties ( 1 sigma) from: 23266105 23 (ERR-1) alpha factor, 23266105 24 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266105 25 epithermal flux for gold, 23266105 26 (ERR-3) effective resonance energy Er, 23266105 27 (ERR-4) Cd transmission factor FCd 23266105 28 (ERR-5) A/ACd -ratio of induced gamma activities, 23266105 29 bare and Cd-covered sample. 23266105 30 (ERR-S) Standard deviation. 23266105 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266105 32 (COREL,23266104) Average data . 23266105 33 ENDBIB 31 0 23266105 34 COMMON 2 3 23266105 35 EN-MIN-NM EN-DN 23266105 36 EV EV 23266105 37 0.55 0.0253 23266105 38 ENDCOMMON 3 0 23266105 39 DATA 8 1 23266105 40 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266105 41 ERR-5 ERR-SYS 23266105 42 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266105 43 PER-CENT PER-CENT 23266105 44 2.72 1.0 1.05 1.0 0.1 0.55 23266105 45 0.55 1.65 23266105 46 ENDDATA 6 0 23266105 47 ENDSUBENT 46 0 2326610599999 SUBENT 23266106 20230215 231423266106 1 BIB 5 11 23266106 2 REACTION (47-AG-107(N,G)47-AG-108,,SIG,,AV) 23266106 3 SIG-0 - the average thermal neutron cross-section . 23266106 4 for neutrons at an average energy of E0=25.3 meV 23266106 5 or velocity v0=2200 m/s. 23266106 6 ANALYSIS Derived from directly measured data. 23266106 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266106 8 Uncertainty on exp. SIG-0 value comes from to the 23266106 9 observed SD between gamma-lines. 23266106 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266106 11 (DEP,23266107) Directly measured data. 23266106 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266106 13 ENDBIB 11 0 23266106 14 COMMON 1 3 23266106 15 EN 23266106 16 EV 23266106 17 0.0253 23266106 18 ENDCOMMON 3 0 23266106 19 DATA 2 1 23266106 20 DATA DATA-ERR 23266106 21 B B 23266106 22 34.3 0.9 23266106 23 ENDDATA 3 0 23266106 24 ENDSUBENT 23 0 2326610699999 SUBENT 23266107 20141210 224123266107 1 BIB 8 30 23266107 2 REACTION (47-AG-107(N,G)47-AG-108,,SIG) 23266107 3 Directly measured thermal neutron cross-section SIG-0 23266107 4 SAMPLE - Provider - IRMM 23266107 5 - Matrix - Foil,Al alloy 23266107 6 Elemental content, % weight - 1. 23266107 7 Average sample thickness, mm - 0.1 23266107 8 - Provider - Goodfellow 23266107 9 - Matrix - Wire 23266107 10 Elemental content, % weight - 99.9 23266107 11 Average sample thickness, mm - 1. 23266107 12 (47-AG-107,NAT=0.51839) 51.839+-0.008 % 23266107 13 DECAY-DATA ((1.)47-AG-108-G,2.37MIN,DG,434.0,0.0050) 23266107 14 ((2.)47-AG-108-G,2.37MIN,DG,618.9,0.0026) 23266107 15 ((3.)47-AG-108-G,2.37MIN,DG,633.0,0.0174) 23266107 16 reference line 23266107 17 METHOD Measurement at channel S84 . 23266107 18 ANALYSIS An thermal neutron cross-section SIG-0 was 23266107 19 extrapolated with aid of the k0-definition, atomic 23266107 20 weight, isotopic composition, the gamma intensities 23266107 21 values. 23266107 22 Defined according to their ADS(activation decay scheme,23266107 23 including decay branching factors). 23266107 24 ADD-RES Measured k0-values with one-sigma uncertainty 23266107 25 E-gamma,keV k0, no-dim.(uncertainty,%) 23266107 26 434.0 1.68E-3 (+-1.0%) 23266107 27 618.9 9.22E-4 (+-1.0%) 23266107 28 633.0 6.05E-3 (+-0.9%) 23266107 29 ERR-ANALYS Uncertainty is not given. 23266107 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266107 31 (COREL,23266106) Average data 23266107 32 ENDBIB 30 0 23266107 33 COMMON 1 3 23266107 34 EN 23266107 35 EV 23266107 36 0.0253 23266107 37 ENDCOMMON 3 0 23266107 38 DATA 2 3 23266107 39 DATA DECAY-FLAG 23266107 40 B NO-DIM 23266107 41 33.5 1. 23266107 42 35.2 2. 23266107 43 34.2 3. 23266107 44 ENDDATA 5 0 23266107 45 ENDSUBENT 44 0 2326610799999 SUBENT 23266108 20230215 231423266108 1 BIB 9 31 23266108 2 REACTION 1((56-BA-130(N,G)56-BA-131,,RI)// 23266108 3 (56-BA-130(N,G)56-BA-131,,SIG)) 23266108 4 2((56-BA-130(N,G)56-BA-131,,RI)// 23266108 5 (56-BA-130(N,G)56-BA-131,,SIG)) 23266108 6 Q0 value (ratio of resonance integral to thermal 23266108 7 neutron activation cross-section) 23266108 8 SAMPLE - Provider - Sigma-Aldrich 23266108 9 Matrix - High purity BaO 23266108 10 Elemental content, % weight - 89.565 23266108 11 Average sample thickness, mm - 0.15 23266108 12 (56-BA-130,NAT=0.00106) 0.106+-0.001 % 23266108 13 METHOD Measurement at channels S84, Y4, X26 . 23266108 14 DECAY-DATA (56-BA-131-M,14.6MIN,DG,123.8,0.2980,DG,133.6,0.0218, 23266108 15 DG,216.1,0.2040,DG,239.6,0.0250,DG,249.4,0.0296, 23266108 16 DG,373.2,0.1440,DG,404.0,0.0134,DG,486.5,0.0215, 23266108 17 DG,496.3,0.4800,DG,585.0,0.0122,DG,620.1,0.0147, 23266108 18 DG,1047.6,0.0134) 23266108 19 (56-BA-131-G,11.50D) 23266108 20 ANALYSIS The Q0 factor was determined by 23266108 21 1- the classical method: through the weighted mean and 23266108 22 observed standard deviation of the 3 irradiation 23266108 23 channels employed (Y4, S84, X26), when inputting Er 23266108 24 factors from the literature. 23266108 25 2- the a-vector method: through the parameters 23266108 26 (m, b) --> determination of the value as well. 23266108 27 ADD-RES Effective resonance Energy was defined by a-vect23266108 28 method to be 58.0 eV ( +-5%, 2sigma). 23266108 29 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266108 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266108 31 1(DEP,23266109) Directly measured data . 23266108 32 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266108 33 ENDBIB 31 0 23266108 34 COMMON 2 3 23266108 35 EN-MIN-NM EN-DN 23266108 36 EV EV 23266108 37 0.55 0.0253 23266108 38 ENDCOMMON 3 0 23266108 39 DATA 4 1 23266108 40 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266108 41 NO-DIM PER-CENT NO-DIM PER-CENT 23266108 42 20.7 3. 21.0 2. 23266108 43 ENDDATA 3 0 23266108 44 ENDSUBENT 43 0 2326610899999 SUBENT 23266109 20141210 224123266109 1 BIB 7 34 23266109 2 REACTION ((56-BA-130(N,G)56-BA-131,,RI)// 23266109 3 (56-BA-130(N,G)56-BA-131,,SIG)) 23266109 4 Q0 value (ratio of resonance integral to thermal 23266109 5 neutron activation cross-section) 23266109 6 SAMPLE - Provider - Sigma-Aldrich 23266109 7 Matrix - High purity BaO 23266109 8 Elemental content, % weight - 89.565 23266109 9 Average sample thickness, mm - 0.15 23266109 10 (56-BA-130,NAT=0.00106) 0.106+-0.001 % 23266109 11 DECAY-DATA (56-BA-131-M,14.6MIN,DG,123.8,0.2980,DG,133.6,0.0218, 23266109 12 DG,216.1,0.2040,DG,239.6,0.0250,DG,249.4,0.0296, 23266109 13 DG,373.2,0.1440,DG,404.0,0.0134,DG,486.5,0.0215, 23266109 14 DG,496.3,0.4800,DG,585.0,0.0122,DG,620.1,0.0147, 23266109 15 DG,1047.6,0.0134) 23266109 16 (56-BA-131-G,11.50D) 23266109 17 FLAG Measurement at channels 23266109 18 (1.) S84, 23266109 19 (2.) Y4, 23266109 20 (3.) X26 23266109 21 ANALYSIS The Q0 factor was determined by the classical method 23266109 22 when inputting effective resonance energy factors 23266109 23 from the literature. 23266109 24 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266109 25 uncertainties ( 1 sigma) from: 23266109 26 (ERR-1) alpha factor, 23266109 27 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266109 28 epithermal flux for gold, 23266109 29 (ERR-3) effective resonance energy Er, 23266109 30 (ERR-4) Cd transmission factor FCd 23266109 31 (ERR-5) A/ACd -ratio of induced gamma activities, 23266109 32 bare and Cd-covered sample. 23266109 33 (ERR-S) Standard deviation. 23266109 34 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266109 35 (COREL,23266108) Average data . 23266109 36 ENDBIB 34 0 23266109 37 COMMON 2 3 23266109 38 EN-MIN-NM EN-DN 23266109 39 EV EV 23266109 40 0.55 0.0253 23266109 41 ENDCOMMON 3 0 23266109 42 DATA 9 3 23266109 43 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266109 44 ERR-5 ERR-SYS FLAG 23266109 45 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266109 46 PER-CENT PER-CENT NO-DIM 23266109 47 20.1 0.6 0.9 1.25 0.0 0.55 23266109 48 1.1 1.95 1. 23266109 49 21.4 0.5 0.35 1.1 0.05 0.6 23266109 50 0.6 1.45 2. 23266109 51 20.1 0.6 0.8 1.3 0.1 0.65 23266109 52 0.5 1.75 3. 23266109 53 ENDDATA 10 0 23266109 54 ENDSUBENT 53 0 2326610999999 SUBENT 23266110 20230215 231423266110 1 BIB 5 12 23266110 2 REACTION (56-BA-130(N,G)56-BA-131,,SIG,,AV) M+G 23266110 3 SIG-0 - the average thermal neutron cross-section . 23266110 4 for neutrons at an average energy of E0=25.3 meV 23266110 5 or velocity v0=2200 m/s. 23266110 6 ANALYSIS Derived from directly measured data. 23266110 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266110 8 Uncertainty on exp. SIG-0 value comes from to the 23266110 9 observed standard deviation between gamma-lines. 23266110 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266110 11 (DEP,23266111) Directly measured data. 23266110 12 HISTORY (20180202A) M.M. DATA misprint was corrected 23266110 13 (20230215A) SD: SF8=AV added to REACTION codes. 23266110 14 ENDBIB 12 0 23266110 15 COMMON 1 3 23266110 16 EN 23266110 17 EV 23266110 18 0.0253 23266110 19 ENDCOMMON 3 0 23266110 20 DATA 2 1 23266110 21 DATA DATA-ERR 23266110 22 B B 23266110 23 8.00 0.19 23266110 24 ENDDATA 3 0 23266110 25 ENDSUBENT 24 0 2326611099999 SUBENT 23266111 20141210 224123266111 1 BIB 8 45 23266111 2 REACTION (56-BA-130(N,G)56-BA-131,,SIG) 23266111 3 Directly measured thermal neutron cross-section SIG-0 23266111 4 SAMPLE - Provider - Sigma-Aldrich 23266111 5 Matrix - High purity BaO 23266111 6 Elemental content, % weight - 89.565 23266111 7 Average sample thickness, mm - 0.15 23266111 8 (56-BA-130,NAT=0.00106) 0.106+-0.001 % 23266111 9 DECAY-DATA ((1.)56-BA-131-M,14.6MIN,DG,123.8,0.2980) 23266111 10 ((2.)56-BA-131-M,14.6MIN,DG,133.6,0.0218) 23266111 11 ((3.)56-BA-131-M,14.6MIN,DG,216.1,0.2040) 23266111 12 ((4.)56-BA-131-M,14.6MIN,DG,239.6,0.0250) 23266111 13 ((5.)56-BA-131-M,14.6MIN,DG,249.4,0.0296) 23266111 14 ((6.)56-BA-131-M,14.6MIN,DG,373.2,0.1440) 23266111 15 ((7.)56-BA-131-M,14.6MIN,DG,404.0,0.0134) 23266111 16 ((8.)56-BA-131-M,14.6MIN,DG,486.5,0.0215) 23266111 17 ((9.)56-BA-131-M,14.6MIN,DG,496.3,0.4800) 23266111 18 reference line. 23266111 19 ((10.)56-BA-131-M,14.6MIN,DG,585.0,0.0122) 23266111 20 ((11.)56-BA-131-M,14.6MIN,DG,620.1,0.0147) 23266111 21 ((12.)56-BA-131-M,14.6MIN,DG,1047.6,0.0134) 23266111 22 (56-BA-131-G,11.50D) 23266111 23 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266111 24 ANALYSIS An thermal neutron cross-section SIG-0 was 23266111 25 extrapolated with aid of the k0-definition, atomic 23266111 26 weight, isotopic composition, the gamma intensities 23266111 27 values. 23266111 28 Defined according to their ADS(activation decay scheme,23266111 29 including decay branching factors). 23266111 30 ADD-RES Measured k0-values with one-sigma uncertainty 23266111 31 E-gamma,keV k0, no-dim.(uncertainty,%) 23266111 32 123.8 3.94E-5 (+-0.2%) 23266111 33 133.6 2.97E-6 (+-0.4%) 23266111 34 216.1 2.59E-5 (+-1.2%) 23266111 35 239.6 3.23E-5 (+-0.7%) 23266111 36 249.4 3.69E-4 (+-1.6%) 23266111 37 373.2 1.82E-5 (+-1.2%) 23266111 38 404.0 1.73E-6 (+-1.3%) 23266111 39 486.5 2.78E-6 (+-1.3%) 23266111 40 496.3 6.15E-5 (+-1.0%) 23266111 41 585.0 1.61E-6 (+-0.9%) 23266111 42 620.1 1.88E-6 (+-0.8%) 23266111 43 1047.6 1.72E-6 (+-1.1%) 23266111 44 ERR-ANALYS Uncertainty is not given. 23266111 45 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266111 46 (COREL,23266110) Average data 23266111 47 ENDBIB 45 0 23266111 48 COMMON 1 3 23266111 49 EN 23266111 50 EV 23266111 51 0.0253 23266111 52 ENDCOMMON 3 0 23266111 53 DATA 2 12 23266111 54 DATA DECAY-FLAG 23266111 55 B NO-DIM 23266111 56 8.19 1. 23266111 57 8.44 2. 23266111 58 7.89 3. 23266111 59 8.00 4. 23266111 60 7.72 5. 23266111 61 7.82 6. 23266111 62 7.97 7. 23266111 63 8.04 8. 23266111 64 7.94 9. 23266111 65 8.13 10. 23266111 66 7.92 11. 23266111 67 7.97 12. 23266111 68 ENDDATA 14 0 23266111 69 ENDSUBENT 68 0 2326611199999 SUBENT 23266112 20230215 231423266112 1 BIB 9 26 23266112 2 REACTION 1((56-BA-132(N,G)56-BA-133-M,,RI)// 23266112 3 (56-BA-132(N,G)56-BA-133-M,,SIG)) 23266112 4 2((56-BA-132(N,G)56-BA-133-M,,RI)// 23266112 5 (56-BA-132(N,G)56-BA-133-M,,SIG)) 23266112 6 Q0 value (ratio of resonance integral to thermal 23266112 7 neutron activation cross-section) 23266112 8 SAMPLE - Provider - Sigma-Aldrich 23266112 9 Matrix - High purity BaO 23266112 10 Elemental content, % weight - 89.565 23266112 11 Average sample thickness, mm - 0.15 23266112 12 (56-BA-132,NAT=0.00101) 0.101+-0.001 % 23266112 13 METHOD Measurement at channels S84, Y4, X26 . 23266112 14 DECAY-DATA (56-BA-133-M,38.9HR,DG,275.9,0.1769) 23266112 15 ANALYSIS The Q0 factor was determined by 23266112 16 1- the classical method: through the weighted mean and 23266112 17 observed standard deviation of the 3 irradiation 23266112 18 channels employed (Y4, S84, X26), when inputting Er 23266112 19 factors from the literature. 23266112 20 2- the a-vector method: through the parameters 23266112 21 (m, b) --> determination of the value as well. 23266112 22 ADD-RES Effective resonance Energy was defined by a-vect23266112 23 method to be 322. eV ( +-4%, 2sigma). 23266112 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266112 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266112 26 1(DEP,23266113) Directly measured data . 23266112 27 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266112 28 ENDBIB 26 0 23266112 29 COMMON 2 3 23266112 30 EN-MIN-NM EN-DN 23266112 31 EV EV 23266112 32 0.55 0.0253 23266112 33 ENDCOMMON 3 0 23266112 34 DATA 4 1 23266112 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266112 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266112 37 4.6 4.5 4.8 2. 23266112 38 ENDDATA 3 0 23266112 39 ENDSUBENT 38 0 2326611299999 SUBENT 23266113 20141210 224123266113 1 BIB 7 29 23266113 2 REACTION ((56-BA-132(N,G)56-BA-133-M,,RI)// 23266113 3 (56-BA-132(N,G)56-BA-133-M,,SIG)) 23266113 4 Q0 value (ratio of resonance integral to thermal 23266113 5 neutron activation cross-section) 23266113 6 SAMPLE - Provider - Sigma-Aldrich 23266113 7 Matrix - High purity BaO 23266113 8 Elemental content, % weight - 89.565 23266113 9 Average sample thickness, mm - 0.15 23266113 10 (56-BA-132,NAT=0.00101) 0.101+-0.001 % 23266113 11 DECAY-DATA (56-BA-133-M,38.9HR,DG,275.9,0.1769) 23266113 12 FLAG Measurement at channels 23266113 13 (1.) S84, 23266113 14 (2.) Y4, 23266113 15 (3.) X26 23266113 16 ANALYSIS The Q0 factor was determined by the classical method 23266113 17 when inputting effective resonance energy factors 23266113 18 from the literature. 23266113 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266113 20 uncertainties ( 1 sigma) from: 23266113 21 (ERR-1) alpha factor, 23266113 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266113 23 epithermal flux for gold, 23266113 24 (ERR-3) effective resonance energy Er, 23266113 25 (ERR-4) Cd transmission factor FCd 23266113 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266113 27 bare and Cd-covered sample. 23266113 28 (ERR-S) Standard deviation. 23266113 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266113 30 (COREL,23266112) Average data . 23266113 31 ENDBIB 29 0 23266113 32 COMMON 2 3 23266113 33 EN-MIN-NM EN-DN 23266113 34 EV EV 23266113 35 0.55 0.0253 23266113 36 ENDCOMMON 3 0 23266113 37 DATA 9 3 23266113 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266113 39 ERR-5 ERR-SYS FLAG 23266113 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266113 41 PER-CENT PER-CENT NO-DIM 23266113 42 5.0 0.5 0.9 1.25 0.0 0.55 23266113 43 1.1 1.95 1. 23266113 44 4.4 0.5 0.35 1.1 0.05 0.6 23266113 45 0.6 1.45 2. 23266113 46 4.7 0.5 0.8 1.3 0.1 0.65 23266113 47 0.5 1.75 3. 23266113 48 ENDDATA 10 0 23266113 49 ENDSUBENT 48 0 2326611399999 SUBENT 23266114 20230215 231423266114 1 BIB 5 11 23266114 2 REACTION (56-BA-132(N,G)56-BA-133-M,,SIG,,AV) 23266114 3 SIG-0 - the average thermal neutron cross-section . 23266114 4 for neutrons at an average energy of E0=25.3 meV 23266114 5 or velocity v0=2200 m/s. 23266114 6 ANALYSIS Derived from directly measured data. 23266114 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266114 8 Uncertainty on exp. SIG-0 value comes from to the 23266114 9 observed SD between gamma-lines. 23266114 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266114 11 (DEP,23266115) Directly measured data. 23266114 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266114 13 ENDBIB 11 0 23266114 14 COMMON 1 3 23266114 15 EN 23266114 16 EV 23266114 17 0.0253 23266114 18 ENDCOMMON 3 0 23266114 19 DATA 2 1 23266114 20 DATA DATA-ERR 23266114 21 B B 23266114 22 0.75 0.01 23266114 23 ENDDATA 3 0 23266114 24 ENDSUBENT 23 0 2326611499999 SUBENT 23266115 20141210 224123266115 1 BIB 8 21 23266115 2 REACTION (56-BA-132(N,G)56-BA-133-M,,SIG) 23266115 3 Directly measured thermal neutron cross-section SIG-0 23266115 4 SAMPLE - Provider - Sigma-Aldrich 23266115 5 Matrix - High purity BaO 23266115 6 Elemental content, % weight - 89.565 23266115 7 Average sample thickness, mm - 0.15 23266115 8 (56-BA-132,NAT=0.00101) 0.101+-0.001 % 23266115 9 DECAY-DATA (56-BA-133-M,38.9HR,DG,275.9,0.1769) 23266115 10 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266115 11 ANALYSIS An thermal neutron cross-section SIG-0 was 23266115 12 extrapolated with aid of the k0-definition, atomic 23266115 13 weight, isotopic composition, the gamma intensities 23266115 14 values. 23266115 15 Defined according to their ADS(activation decay scheme,23266115 16 including decay branching factors). 23266115 17 ADD-RES Measured k0-values with one-sigma uncertainty 23266115 18 E-gamma,keV k0, no-dim.(uncertainty,%) 23266115 19 275.9 2.04E-6 (+-0.7%) 23266115 20 ERR-ANALYS Uncertainty is not given. 23266115 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266115 22 (COREL,23266114) Average data 23266115 23 ENDBIB 21 0 23266115 24 COMMON 1 3 23266115 25 EN 23266115 26 EV 23266115 27 0.0253 23266115 28 ENDCOMMON 3 0 23266115 29 DATA 1 1 23266115 30 DATA 23266115 31 B 23266115 32 0.75 23266115 33 ENDDATA 3 0 23266115 34 ENDSUBENT 33 0 2326611599999 SUBENT 23266116 20230215 231423266116 1 BIB 9 26 23266116 2 REACTION 1((56-BA-134(N,G)56-BA-135-M,,RI)// 23266116 3 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23266116 4 2((56-BA-134(N,G)56-BA-135-M,,RI)// 23266116 5 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23266116 6 Q0 value (ratio of resonance integral to thermal 23266116 7 neutron activation cross-section) 23266116 8 SAMPLE - Provider - Sigma-Aldrich 23266116 9 Matrix - High purity BaO 23266116 10 Elemental content, % weight - 89.565 23266116 11 Average sample thickness, mm - 0.15 23266116 12 (56-BA-134,NAT=0.02417) 2.417+-0.018 % 23266116 13 METHOD Measurement at channels S84, Y4, X26 . 23266116 14 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.1600) 23266116 15 ANALYSIS The Q0 factor was determined by 23266116 16 1- the classical method: through the weighted mean and 23266116 17 observed standard deviation of the 3 irradiation 23266116 18 channels employed (Y4, S84, X26), when inputting Er 23266116 19 factors from the literature. 23266116 20 2- the a-vector method: through the parameters 23266116 21 (m, b) --> determination of the value as well. 23266116 22 ADD-RES Effective resonance Energy was defined by a-vect23266116 23 method to be 4247.eV ( +-10%, 2sigma). 23266116 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266116 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266116 26 1(DEP,23266117) Directly measured data . 23266116 27 HISTORY (20180202A) M.M. DATA misprint was corrected 23266116 28 ENDBIB 26 0 23266116 29 COMMON 2 3 23266116 30 EN-MIN-NM EN-DN 23266116 31 EV EV 23266116 32 0.55 0.0253 23266116 33 ENDCOMMON 3 0 23266116 34 DATA 4 1 23266116 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266116 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266116 37 51.6 3.5 50.7 3.5 23266116 38 ENDDATA 3 0 23266116 39 ENDSUBENT 38 0 2326611699999 SUBENT 23266117 20141210 224123266117 1 BIB 7 29 23266117 2 REACTION ((56-BA-134(N,G)56-BA-135-M,,RI)// 23266117 3 (56-BA-134(N,G)56-BA-135-M,,SIG)) 23266117 4 Q0 value (ratio of resonance integral to thermal 23266117 5 neutron activation cross-section) 23266117 6 SAMPLE - Provider - Sigma-Aldrich 23266117 7 Matrix - High purity BaO 23266117 8 Elemental content, % weight - 89.565 23266117 9 Average sample thickness, mm - 0.15 23266117 10 (56-BA-134,NAT=0.02417) 2.417+-0.018 % 23266117 11 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.1600) 23266117 12 FLAG Measurement at channels 23266117 13 (1.) S84, 23266117 14 (2.) Y4, 23266117 15 (3.) X26 23266117 16 ANALYSIS The Q0 factor was determined by the classical method 23266117 17 when inputting effective resonance energy factors 23266117 18 from the literature. 23266117 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266117 20 uncertainties ( 1 sigma) from: 23266117 21 (ERR-1) alpha factor, 23266117 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266117 23 epithermal flux for gold, 23266117 24 (ERR-3) effective resonance energy Er, 23266117 25 (ERR-4) Cd transmission factor FCd 23266117 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266117 27 bare and Cd-covered sample. 23266117 28 (ERR-S) Standard deviation. 23266117 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266117 30 (COREL,23266116) Average data . 23266117 31 ENDBIB 29 0 23266117 32 COMMON 2 3 23266117 33 EN-MIN-NM EN-DN 23266117 34 EV EV 23266117 35 0.55 0.0253 23266117 36 ENDCOMMON 3 0 23266117 37 DATA 9 3 23266117 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266117 39 ERR-5 ERR-SYS FLAG 23266117 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266117 41 PER-CENT PER-CENT NO-DIM 23266117 42 52.4 0.5 2.0 1.5 0.25 0.8 23266117 43 1.25 2.9 1. 23266117 44 49.6 0.5 1.35 1.6 0.35 0.65 23266117 45 1.1 2.5 2. 23266117 46 53.5 0.5 1.8 1.65 0.45 0.7 23266117 47 1.05 2.8 3. 23266117 48 ENDDATA 10 0 23266117 49 ENDSUBENT 48 0 2326611799999 SUBENT 23266118 20230215 231423266118 1 BIB 5 11 23266118 2 REACTION (56-BA-134(N,G)56-BA-135-M,,SIG,,AV) 23266118 3 SIG-0 - the average thermal neutron cross-section . 23266118 4 for neutrons at an average energy of E0=25.3 meV 23266118 5 or velocity v0=2200 m/s. 23266118 6 ANALYSIS Derived from directly measured data. 23266118 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266118 8 Uncertainty on exp. SIG-0 value comes from to the 23266118 9 observed SD between gamma-lines. 23266118 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266118 11 (DEP,23266119) Directly measured data. 23266118 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266118 13 ENDBIB 11 0 23266118 14 COMMON 1 3 23266118 15 EN 23266118 16 EV 23266118 17 0.0253 23266118 18 ENDCOMMON 3 0 23266118 19 DATA 2 1 23266118 20 DATA DATA-ERR 23266118 21 B B 23266118 22 0.059 0.001 23266118 23 ENDDATA 3 0 23266118 24 ENDSUBENT 23 0 2326611899999 SUBENT 23266119 20141210 224123266119 1 BIB 8 21 23266119 2 REACTION (56-BA-134(N,G)56-BA-135-M,,SIG) 23266119 3 Directly measured thermal neutron cross-section SIG-0 23266119 4 SAMPLE - Provider - Sigma-Aldrich 23266119 5 Matrix - High purity BaO 23266119 6 Elemental content, % weight - 89.565 23266119 7 Average sample thickness, mm - 0.15 23266119 8 (56-BA-134,NAT=0.02417) 2.417+-0.018 % 23266119 9 DECAY-DATA (56-BA-135-M,28.7HR,DG,268.3,0.1600) 23266119 10 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266119 11 ANALYSIS An thermal neutron cross-section SIG-0 was 23266119 12 extrapolated with aid of the k0-definition, atomic 23266119 13 weight, isotopic composition, the gamma intensities 23266119 14 values. 23266119 15 Defined according to their ADS(activation decay scheme,23266119 16 including decay branching factors). 23266119 17 ADD-RES Measured k0-values with one-sigma uncertainty 23266119 18 E-gamma,keV k0, no-dim.(uncertainty,%) 23266119 19 268.3 3.47E-6 (+-0.3%) 23266119 20 ERR-ANALYS Uncertainty is not given. 23266119 21 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266119 22 (COREL,23266118) Average data 23266119 23 ENDBIB 21 0 23266119 24 COMMON 1 3 23266119 25 EN 23266119 26 EV 23266119 27 0.0253 23266119 28 ENDCOMMON 3 0 23266119 29 DATA 1 1 23266119 30 DATA 23266119 31 B 23266119 32 0.059 23266119 33 ENDDATA 3 0 23266119 34 ENDSUBENT 33 0 2326611999999 SUBENT 23266120 20230215 231423266120 1 BIB 10 30 23266120 2 REACTION 1((56-BA-138(N,G)56-BA-139,,RI,,AV)// 23266120 3 (56-BA-138(N,G)56-BA-139,,SIG,,AV)) 23266120 4 2((56-BA-138(N,G)56-BA-139,,RI)// 23266120 5 (56-BA-138(N,G)56-BA-139,,SIG)) 23266120 6 Q0 value (ratio of resonance integral to thermal 23266120 7 neutron activation cross-section) 23266120 8 SAMPLE - Provider - Sigma-Aldrich 23266120 9 Matrix - High purity BaO 23266120 10 Elemental content, % weight - 89.565 23266120 11 Average sample thickness, mm - 0.15 23266120 12 (56-BA-138,NAT=0.71698) 71.698+-0.042 % 23266120 13 METHOD Measurement at channels S84, Y4, X26 . 23266120 14 DECAY-DATA (56-BA-139,83.06MIN,DG,165.9,0.2376,DG,1420.5,0.00261) 23266120 15 ANALYSIS The Q0 factor was determined by 23266120 16 1- the classical method: through the weighted mean and 23266120 17 observed standard deviation of the 3 irradiation 23266120 18 channels employed (S84, X26), when inputting Er 23266120 19 factors from the literature. 23266120 20 2- the a-vector method: through the parameters 23266120 21 (m, b) --> determination of the value as well. 23266120 22 ADD-RES Effective resonance Energy was defined by a-vect23266120 23 method to be 1323778 eV ( +-50%, 2sigma). 23266120 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266120 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266120 26 1(DEP,23266121) Directly measured data . 23266120 27 COMMENT Of compiler M.M. 23266120 28 DATA 2 uncertainty in Suppl.Material is given as 29% 23266120 29 - looks like to much, if take into account the 23266120 30 uncertainties given in Subent 117. 23266120 31 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266120 32 ENDBIB 30 0 23266120 33 COMMON 2 3 23266120 34 EN-MIN-NM EN-DN 23266120 35 EV EV 23266120 36 0.55 0.0253 23266120 37 ENDCOMMON 3 0 23266120 38 DATA 4 1 23266120 39 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266120 40 NO-DIM PER-CENT NO-DIM PER-CENT 23266120 41 1.04 14.5 1.20 2.5 23266120 42 ENDDATA 3 0 23266120 43 ENDSUBENT 42 0 2326612099999 SUBENT 23266121 20141210 224123266121 1 BIB 7 28 23266121 2 REACTION ((56-BA-138(N,G)56-BA-139,,RI)// 23266121 3 (56-BA-138(N,G)56-BA-139,,SIG)) 23266121 4 Q0 value (ratio of resonance integral to thermal 23266121 5 neutron activation cross-section) 23266121 6 SAMPLE - Provider - Sigma-Aldrich 23266121 7 Matrix - High purity BaO 23266121 8 Elemental content, % weight - 89.565 23266121 9 Average sample thickness, mm - 0.15 23266121 10 (56-BA-138,NAT=0.71698) 71.698+-0.042 % 23266121 11 DECAY-DATA (56-BA-139,83.06MIN,DG,165.9,0.2376,DG,1420.5,0.00261) 23266121 12 FLAG Measurement at channels 23266121 13 (1.) S84, 23266121 14 (2.) X26 23266121 15 ANALYSIS The Q0 factor was determined by the classical method 23266121 16 when inputting effective resonance energy factors 23266121 17 from the literature. 23266121 18 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266121 19 uncertainties ( 1 sigma) from: 23266121 20 (ERR-1) alpha factor, 23266121 21 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266121 22 epithermal flux for gold, 23266121 23 (ERR-3) effective resonance energy Er, 23266121 24 (ERR-4) Cd transmission factor FCd 23266121 25 (ERR-5) A/ACd -ratio of induced gamma activities, 23266121 26 bare and Cd-covered sample. 23266121 27 (ERR-S) Standard deviation. 23266121 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266121 29 (COREL,23266120) Average data . 23266121 30 ENDBIB 28 0 23266121 31 COMMON 2 3 23266121 32 EN-MIN-NM EN-DN 23266121 33 EV EV 23266121 34 0.55 0.0253 23266121 35 ENDCOMMON 3 0 23266121 36 DATA 9 2 23266121 37 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266121 38 ERR-5 ERR-SYS FLAG 23266121 39 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266121 40 PER-CENT PER-CENT NO-DIM 23266121 41 1.20 0.5 0.65 1.25 0.25 0.55 23266121 42 1.1 1.9 1. 23266121 43 0.90 0.5 0.6 1.3 0.6 0.65 23266121 44 0.5 1.75 2. 23266121 45 ENDDATA 8 0 23266121 46 ENDSUBENT 45 0 2326612199999 SUBENT 23266122 20230215 231423266122 1 BIB 5 11 23266122 2 REACTION (56-BA-138(N,G)56-BA-139,,SIG,,AV) 23266122 3 SIG-0 - the average thermal neutron cross-section . 23266122 4 for neutrons at an average energy of E0=25.3 meV 23266122 5 or velocity v0=2200 m/s. 23266122 6 ANALYSIS Derived from directly measured data. 23266122 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266122 8 Uncertainty on exp. SIG-0 value comes from to the 23266122 9 observed SD between gamma-lines. 23266122 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266122 11 (DEP,23266123) Directly measured data. 23266122 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266122 13 ENDBIB 11 0 23266122 14 COMMON 1 3 23266122 15 EN 23266122 16 EV 23266122 17 0.0253 23266122 18 ENDCOMMON 3 0 23266122 19 DATA 2 1 23266122 20 DATA DATA-ERR 23266122 21 B B 23266122 22 0.403 0.001 23266122 23 ENDDATA 3 0 23266122 24 ENDSUBENT 23 0 2326612299999 SUBENT 23266123 20141210 224123266123 1 BIB 8 23 23266123 2 REACTION (56-BA-138(N,G)56-BA-139,,SIG) 23266123 3 Directly measured thermal neutron cross-section SIG-0 23266123 4 SAMPLE - Provider - Sigma-Aldrich 23266123 5 Matrix - High purity BaO 23266123 6 Elemental content, % weight - 89.565 23266123 7 Average sample thickness, mm - 0.15 23266123 8 (56-BA-138,NAT=0.71698) 71.698+-0.042 % 23266123 9 DECAY-DATA ((1.)56-BA-139,83.06MIN,DG,165.9,0.2376) 23266123 10 ((2.)56-BA-139,83.06MIN,DG,1420.5,0.00261) 23266123 11 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266123 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266123 13 extrapolated with aid of the k0-definition, atomic 23266123 14 weight, isotopic composition, the gamma intensities 23266123 15 values. 23266123 16 Defined according to their ADS(activation decay scheme,23266123 17 including decay branching factors). 23266123 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266123 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266123 20 165.9 1.05E-3 (+-1.0%) 23266123 21 1420.5 1.15E-5 (+-0.6%) 23266123 22 ERR-ANALYS Uncertainty is not given. 23266123 23 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266123 24 (COREL,23266122) Average data 23266123 25 ENDBIB 23 0 23266123 26 COMMON 1 3 23266123 27 EN 23266123 28 EV 23266123 29 0.0253 23266123 30 ENDCOMMON 3 0 23266123 31 DATA 2 2 23266123 32 DATA DECAY-FLAG 23266123 33 B NO-DIM 23266123 34 0.403 1. 23266123 35 0.402 2. 23266123 36 ENDDATA 4 0 23266123 37 ENDSUBENT 36 0 2326612399999 SUBENT 23266124 20230215 231423266124 1 BIB 9 29 23266124 2 REACTION 1((57-LA-139(N,G)57-LA-140,,RI,,AV)// 23266124 3 (57-LA-139(N,G)57-LA-140,,SIG,,AV)) 23266124 4 2((57-LA-139(N,G)57-LA-140,,RI)// 23266124 5 (57-LA-139(N,G)57-LA-140,,SIG)) 23266124 6 Q0 value (ratio of resonance integral to thermal 23266124 7 neutron activation cross-section) 23266124 8 SAMPLE - Provider - IRMM 23266124 9 Matrix - Foil,Al alloy 23266124 10 Elemental content, % weight - 1. 23266124 11 Average sample thickness, mm - 0.1 23266124 12 (57-LA-139,NAT=0.99911) 99.911+-0.001 % 23266124 13 METHOD Measurement at channels S84, Y4, X26 . 23266124 14 DECAY-DATA (57-LA-140,1.6786D,DG,328.8,0.208,DG,423.5,0.02995, 23266124 15 DG,487.0,0.461,DG,751.6,0.04392,DG,815.8,0.2372, 23266124 16 DG,867.8,0.0558,DG,919.6,0.0273,DG,925.2,0.0704, 23266124 17 DG,1596.2,0.954) 23266124 18 ANALYSIS The Q0 factor was determined by 23266124 19 1- the classical method: through the weighted mean and 23266124 20 observed standard deviation of the 3 irradiation 23266124 21 channels employed (Y4, S84, X26), when inputting Er 23266124 22 factors from the literature. 23266124 23 2- the a-vector method: through the parameters 23266124 24 (m, b) --> determination of the value as well. 23266124 25 ADD-RES Effective resonance Energy was defined by a-vect23266124 26 method to be 67.3 eV ( +-5%, 2sigma). 23266124 27 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266124 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266124 29 1(DEP,23266125) Directly measured data . 23266124 30 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266124 31 ENDBIB 29 0 23266124 32 COMMON 2 3 23266124 33 EN-MIN-NM EN-DN 23266124 34 EV EV 23266124 35 0.55 0.0253 23266124 36 ENDCOMMON 3 0 23266124 37 DATA 4 1 23266124 38 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266124 39 NO-DIM PER-CENT NO-DIM PER-CENT 23266124 40 1.16 1. 1.15 2. 23266124 41 ENDDATA 3 0 23266124 42 ENDSUBENT 41 0 2326612499999 SUBENT 23266125 20141210 224123266125 1 BIB 7 32 23266125 2 REACTION ((57-LA-139(N,G)57-LA-140,,RI)// 23266125 3 (57-LA-139(N,G)57-LA-140,,SIG)) 23266125 4 Q0 value (ratio of resonance integral to thermal 23266125 5 neutron activation cross-section) 23266125 6 SAMPLE - Provider - Sigma-Aldrich 23266125 7 Matrix - High purity BaO 23266125 8 Elemental content, % weight - 89.565 23266125 9 Average sample thickness, mm - 0.15 23266125 10 (57-LA-139,NAT=0.99911) 99.911+-0.001 % 23266125 11 DECAY-DATA (57-LA-140,1.6786D,DG,328.8,0.208,DG,423.5,0.02995, 23266125 12 DG,487.0,0.461,DG,751.6,0.04392,DG,815.8,0.2372, 23266125 13 DG,867.8,0.0558,DG,919.6,0.0273,DG,925.2,0.0704, 23266125 14 DG,1596.2,0.954) 23266125 15 FLAG Measurement at channels 23266125 16 (1.) S84, 23266125 17 (2.) Y4, 23266125 18 (3.) X26 23266125 19 ANALYSIS The Q0 factor was determined by the classical method 23266125 20 when inputting effective resonance energy factors 23266125 21 from the literature. 23266125 22 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266125 23 uncertainties ( 1 sigma) from: 23266125 24 (ERR-1) alpha factor, 23266125 25 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266125 26 epithermal flux for gold, 23266125 27 (ERR-3) effective resonance energy Er, 23266125 28 (ERR-4) Cd transmission factor FCd 23266125 29 (ERR-5) A/ACd -ratio of induced gamma activities, 23266125 30 bare and Cd-covered sample. 23266125 31 (ERR-S) Standard deviation. 23266125 32 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266125 33 (COREL,23266124) Average data . 23266125 34 ENDBIB 32 0 23266125 35 COMMON 2 3 23266125 36 EN-MIN-NM EN-DN 23266125 37 EV EV 23266125 38 0.55 0.0253 23266125 39 ENDCOMMON 3 0 23266125 40 DATA 9 3 23266125 41 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266125 42 ERR-5 ERR-SYS FLAG 23266125 43 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266125 44 PER-CENT PER-CENT NO-DIM 23266125 45 1.16 0.75 0.8 1.1 0.1 0.55 23266125 46 0.65 1.6 1. 23266125 47 1.15 1.95 0.55 1.35 0.1 0.55 23266125 48 0.65 1.7 2. 23266125 49 1.17 0.85 1.15 1.7 0.15 0.6 23266125 50 0.7 2.25 3. 23266125 51 ENDDATA 10 0 23266125 52 ENDSUBENT 51 0 2326612599999 SUBENT 23266126 20230215 231423266126 1 BIB 5 11 23266126 2 REACTION (57-LA-139(N,G)57-LA-140,,SIG,,AV) 23266126 3 SIG-0 - the average thermal neutron cross-section . 23266126 4 for neutrons at an average energy of E0=25.3 meV 23266126 5 or velocity v0=2200 m/s. 23266126 6 ANALYSIS Derived from directly measured data. 23266126 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266126 8 Uncertainty on exp. SIG-0 value comes from to the 23266126 9 observed SD between gamma-lines. 23266126 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266126 11 (DEP,23266127) Directly measured data. 23266126 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266126 13 ENDBIB 11 0 23266126 14 COMMON 1 3 23266126 15 EN 23266126 16 EV 23266126 17 0.0253 23266126 18 ENDCOMMON 3 0 23266126 19 DATA 2 1 23266126 20 DATA DATA-ERR 23266126 21 B B 23266126 22 9.25 0.04 23266126 23 ENDDATA 3 0 23266126 24 ENDSUBENT 23 0 2326612699999 SUBENT 23266127 20141210 224123266127 1 BIB 8 37 23266127 2 REACTION (57-LA-139(N,G)57-LA-140,,SIG) 23266127 3 Directly measured thermal neutron cross-section SIG-0 23266127 4 SAMPLE - Provider - Sigma-Aldrich 23266127 5 Matrix - High purity BaO 23266127 6 Elemental content, % weight - 89.565 23266127 7 Average sample thickness, mm - 0.15 23266127 8 (57-LA-139,NAT=0.99911) 99.911+-0.001 % 23266127 9 DECAY-DATA ((1.)57-LA-140,1.6786D,DG,328.8,0.208) 23266127 10 ((2.)57-LA-140,1.6786D,DG,423.5,0.02995) 23266127 11 ((3.)57-LA-140,1.6786D,DG,487.0,0.461) reference line 23266127 12 ((4.)57-LA-140,1.6786D,DG,751.6,0.04392) 23266127 13 ((5.)57-LA-140,1.6786D,DG,815.8,0.2372) 23266127 14 ((6.)57-LA-140,1.6786D,DG,867.8,0.0558) 23266127 15 ((7.)57-LA-140,1.6786D,DG,919.6,0.0273) 23266127 16 ((8.)57-LA-140,1.6786D,DG,925.2,0.0704) 23266127 17 ((9.)57-LA-140,1.6786D,DG,1596.2,0.954) 23266127 18 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266127 19 ANALYSIS An thermal neutron cross-section SIG-0 was 23266127 20 extrapolated with aid of the k0-definition, atomic 23266127 21 weight, isotopic composition, the gamma intensities 23266127 22 values. 23266127 23 Defined according to their ADS(activation decay scheme,23266127 24 including decay branching factors). 23266127 25 ADD-RES Measured k0-values with one-sigma uncertainty 23266127 26 E-gamma,keV k0, no-dim.(uncertainty,%) 23266127 27 328.8 2.88E-2 (+-1.1%) 23266127 28 423.5 4.16E-3 (+-1.4%) 23266127 29 487.0 6.35E-2 (+-0.1%) 23266127 30 751.6 6.12E-3 (+-1.6%) 23266127 31 815.8 3.29E-2 (+-1.0%) 23266127 32 867.8 7.78E-3 (+-0.5%) 23266127 33 919.6 3.78E-3 (+-0.7%) 23266127 34 925.2 9.83E-3 (+-0.7%) 23266127 35 1596.2 1.33E-1 (+-0.4%) 23266127 36 ERR-ANALYS Uncertainty is not given. 23266127 37 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266127 38 (COREL,23266126) Average data 23266127 39 ENDBIB 37 0 23266127 40 COMMON 1 3 23266127 41 EN 23266127 42 EV 23266127 43 0.0253 23266127 44 ENDCOMMON 3 0 23266127 45 DATA 2 9 23266127 46 DATA DECAY-FLAG 23266127 47 B NO-DIM 23266127 48 9.22 1. 23266127 49 9.23 2. 23266127 50 9.16 3. 23266127 51 9.27 4. 23266127 52 9.24 5. 23266127 53 9.27 6. 23266127 54 9.22 7. 23266127 55 9.29 8. 23266127 56 9.30 9. 23266127 57 ENDDATA 11 0 23266127 58 ENDSUBENT 57 0 2326612799999 SUBENT 23266128 20230215 231423266128 1 BIB 9 27 23266128 2 REACTION 1((59-PR-141(N,G)59-PR-142,,RI,,AV)// 23266128 3 (59-PR-141(N,G)59-PR-142,,SIG,,AV)) 23266128 4 2((59-PR-141(N,G)59-PR-142,,RI)// 23266128 5 (59-PR-141(N,G)59-PR-142,,SIG)) 23266128 6 Q0 value (ratio of resonance integral to thermal 23266128 7 neutron activation cross-section) 23266128 8 SAMPLE - Provider - IRMM 23266128 9 Matrix - Wire,Al alloy 23266128 10 Elemental content, % weight - 1.25 23266128 11 Average sample thickness, mm - 1. 23266128 12 (59-PR-141,NAT=1.00) 23266128 13 METHOD Measurement at channels S84, Y4, X26 . 23266128 14 DECAY-DATA (59-PR-142-G,19.12HR,DG,1575.6,0.037) 23266128 15 (59-PR-142-M,14.6MIN) 23266128 16 ANALYSIS The Q0 factor was determined by 23266128 17 1- the classical method: through the weighted mean and 23266128 18 observed standard deviation of the 3 irradiation 23266128 19 channels employed (Y4, S84, X26), when inputting Er 23266128 20 factors from the literature. 23266128 21 2- the a-vector method: through the parameters 23266128 22 (m, b) --> determination of the value as well. 23266128 23 ADD-RES Effective resonance Energy was defined by a-vect23266128 24 method to be 123. eV ( +-9%, 2sigma). 23266128 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266128 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266128 27 1(DEP,23266129) Directly measured data . 23266128 28 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266128 29 ENDBIB 27 0 23266128 30 COMMON 2 3 23266128 31 EN-MIN-NM EN-DN 23266128 32 EV EV 23266128 33 0.55 0.0253 23266128 34 ENDCOMMON 3 0 23266128 35 DATA 4 1 23266128 36 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266128 37 NO-DIM PER-CENT NO-DIM PER-CENT 23266128 38 1.41 2.5 1.37 2. 23266128 39 ENDDATA 3 0 23266128 40 ENDSUBENT 39 0 2326612899999 SUBENT 23266129 20141210 224123266129 1 BIB 7 30 23266129 2 REACTION ((59-PR-141(N,G)59-PR-142,,RI)// 23266129 3 (59-PR-141(N,G)59-PR-142,,SIG)) 23266129 4 Q0 value (ratio of resonance integral to thermal 23266129 5 neutron activation cross-section) 23266129 6 SAMPLE - Provider - IRMM 23266129 7 Matrix - Wire,Al alloy 23266129 8 Elemental content, % weight - 1.25 23266129 9 Average sample thickness, mm - 1. 23266129 10 (59-PR-141,NAT=1.00) 23266129 11 DECAY-DATA (59-PR-142-G,19.12HR,DG,1575.6,0.037) 23266129 12 (59-PR-142-M,14.6MIN) 23266129 13 FLAG Measurement at channels 23266129 14 (1.) S84, 23266129 15 (2.) Y4, 23266129 16 (3.) X26 23266129 17 ANALYSIS The Q0 factor was determined by the classical method 23266129 18 when inputting effective resonance energy factors 23266129 19 from the literature. 23266129 20 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266129 21 uncertainties ( 1 sigma) from: 23266129 22 (ERR-1) alpha factor, 23266129 23 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266129 24 epithermal flux for gold, 23266129 25 (ERR-3) effective resonance energy Er, 23266129 26 (ERR-4) Cd transmission factor FCd 23266129 27 (ERR-5) A/ACd -ratio of induced gamma activities, 23266129 28 bare and Cd-covered sample. 23266129 29 (ERR-S) Standard deviation. 23266129 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266129 31 (COREL,23266128) Average data . 23266129 32 ENDBIB 30 0 23266129 33 COMMON 2 3 23266129 34 EN-MIN-NM EN-DN 23266129 35 EV EV 23266129 36 0.55 0.0253 23266129 37 ENDCOMMON 3 0 23266129 38 DATA 9 3 23266129 39 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266129 40 ERR-5 ERR-SYS FLAG 23266129 41 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266129 42 PER-CENT PER-CENT NO-DIM 23266129 43 1.36 0.55 1.2 1.4 0.0 0.55 23266129 44 0.65 2.05 1. 23266129 45 1.43 1.8 0.45 1.0 0.0 0.55 23266129 46 0.65 1.4 2. 23266129 47 1.46 3.0 1.15 2.5 0.05 0.6 23266129 48 0.7 2.9 3. 23266129 49 ENDDATA 10 0 23266129 50 ENDSUBENT 49 0 2326612999999 SUBENT 23266130 20230215 231423266130 1 BIB 5 11 23266130 2 REACTION (59-PR-141(N,G)59-PR-142,,SIG,,AV) M+G 23266130 3 SIG-0 - the average thermal neutron cross-section . 23266130 4 for neutrons at an average energy of E0=25.3 meV 23266130 5 or velocity v0=2200 m/s. 23266130 6 ANALYSIS Derived from directly measured data. 23266130 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266130 8 Uncertainty on exp. SIG-0 value comes from to the 23266130 9 observed SD between gamma-lines. 23266130 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266130 11 (DEP,23266131) Directly measured data. 23266130 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266130 13 ENDBIB 11 0 23266130 14 COMMON 1 3 23266130 15 EN 23266130 16 EV 23266130 17 0.0253 23266130 18 ENDCOMMON 3 0 23266130 19 DATA 2 1 23266130 20 DATA DATA-ERR 23266130 21 B B 23266130 22 11.3 0.1 23266130 23 ENDDATA 3 0 23266130 24 ENDSUBENT 23 0 2326613099999 SUBENT 23266131 20141210 224123266131 1 BIB 8 22 23266131 2 REACTION (59-PR-141(N,G)59-PR-142,,SIG) M+G 23266131 3 Directly measured thermal neutron cross-section SIG-0 23266131 4 SAMPLE - Provider - IRMM 23266131 5 Matrix - Wire,Al alloy 23266131 6 Elemental content, % weight - 1.25 23266131 7 Average sample thickness, mm - 1. 23266131 8 (59-PR-141,NAT=1.00) 23266131 9 DECAY-DATA (59-PR-142-G,19.12HR,DG,1575.6,0.037) 23266131 10 (59-PR-142-M,14.6MIN) 23266131 11 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266131 12 ANALYSIS An thermal neutron cross-section SIG-0 was 23266131 13 extrapolated with aid of the k0-definition, atomic 23266131 14 weight, isotopic composition, the gamma intensities 23266131 15 values. 23266131 16 Defined according to their ADS(activation decay scheme,23266131 17 including decay branching factors). 23266131 18 ADD-RES Measured k0-values with one-sigma uncertainty 23266131 19 E-gamma,keV k0, no-dim.(uncertainty,%) 23266131 20 1575.6 6.19E-3 (+-0.5%) 23266131 21 ERR-ANALYS Uncertainty is not given. 23266131 22 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266131 23 (COREL,23266130) Average data 23266131 24 ENDBIB 22 0 23266131 25 COMMON 1 3 23266131 26 EN 23266131 27 EV 23266131 28 0.0253 23266131 29 ENDCOMMON 3 0 23266131 30 DATA 1 1 23266131 31 DATA 23266131 32 B 23266131 33 11.3 23266131 34 ENDDATA 3 0 23266131 35 ENDSUBENT 34 0 2326613199999 SUBENT 23266132 20230215 231423266132 1 BIB 9 27 23266132 2 REACTION 1((62-SM-152(N,G)62-SM-153,,RI,,AV)// 23266132 3 (62-SM-152(N,G)62-SM-153,,SIG,,AV)) 23266132 4 2((62-SM-152(N,G)62-SM-153,,RI)// 23266132 5 (62-SM-152(N,G)62-SM-153,,SIG)) 23266132 6 Q0 value (ratio of resonance integral to thermal 23266132 7 neutron activation cross-section) 23266132 8 SAMPLE - Provider - IRMM 23266132 9 Matrix - Wire,Al alloy 23266132 10 Elemental content, % weight - 0.008 23266132 11 Average sample thickness, mm - 0.37 23266132 12 (62-SM-152,NAT=0.2675) 26.75+-0.16 % 23266132 13 METHOD Measurement at channels S84, Y4, X26 . 23266132 14 DECAY-DATA (62-SM-153,1.9375D,DG,69.7,0.04691,DG,97.4,0.00779, 23266132 15 DG,103.2,0.2919) 23266132 16 ANALYSIS The Q0 factor was determined by 23266132 17 1- the classical method: through the weighted mean and 23266132 18 observed standard deviation of the 3 irradiation 23266132 19 channels employed (Y4, S84, X26), when inputting Er 23266132 20 factors from the literature. 23266132 21 2- the a-vector method: through the parameters 23266132 22 (m, b) --> determination of the value as well. 23266132 23 ADD-RES Effective resonance Energy was defined by a-vect23266132 24 method to be 8.48 eV ( +-9%, 2sigma). 23266132 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266132 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266132 27 2(DEP,23266133) Directly measured data . 23266132 28 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266132 29 ENDBIB 27 0 23266132 30 COMMON 2 3 23266132 31 EN-MIN-NM EN-DN 23266132 32 EV EV 23266132 33 0.55 0.0253 23266132 34 ENDCOMMON 3 0 23266132 35 DATA 4 1 23266132 36 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266132 37 NO-DIM PER-CENT NO-DIM PER-CENT 23266132 38 14.6 1.5 14.7 2. 23266132 39 ENDDATA 3 0 23266132 40 ENDSUBENT 39 0 2326613299999 SUBENT 23266133 20180202 226823266133 1 BIB 8 32 23266133 2 REACTION ((62-SM-152(N,G)62-SM-153,,RI)// 23266133 3 (62-SM-152(N,G)62-SM-153,,SIG)) 23266133 4 Q0 value (ratio of resonance integral to thermal 23266133 5 neutron activation cross-section) 23266133 6 SAMPLE - Provider - IRMM 23266133 7 Matrix - Wire,Al alloy 23266133 8 Elemental content, % weight - 0.008 23266133 9 Average sample thickness, mm - 0.37 23266133 10 (62-SM-152,NAT=0.2675) 26.75+-0.16 % 23266133 11 DECAY-DATA (62-SM-153,1.9375D,DG,69.7,0.04691, 23266133 12 DG,97.4,0.00779, 23266133 13 DG,103.2,0.2919) 23266133 14 FLAG Measurement at channels 23266133 15 (1.) S84, 23266133 16 (2.) Y4, 23266133 17 (3.) X26 23266133 18 ANALYSIS The Q0 factor was determined by the classical method 23266133 19 when inputting effective resonance energy factors 23266133 20 from the literature. 23266133 21 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266133 22 uncertainties ( 1 sigma) from: 23266133 23 (ERR-1) alpha factor, 23266133 24 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266133 25 epithermal flux for gold, 23266133 26 (ERR-3) effective resonance energy Er, 23266133 27 (ERR-4) Cd transmission factor FCd 23266133 28 (ERR-5) A/ACd -ratio of induced gamma activities, 23266133 29 bare and Cd-covered sample. 23266133 30 (ERR-S) Standard deviation. 23266133 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266133 32 (COREL,23266132) Average data . 23266133 33 HISTORY (20180202A) M.M. DATA misprint was corrected 23266133 34 ENDBIB 32 0 23266133 35 COMMON 2 3 23266133 36 EN-MIN-NM EN-DN 23266133 37 EV EV 23266133 38 0.55 0.0253 23266133 39 ENDCOMMON 3 0 23266133 40 DATA 9 3 23266133 41 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266133 42 ERR-5 ERR-SYS FLAG 23266133 43 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266133 44 PER-CENT PER-CENT NO-DIM 23266133 45 14.8 0.3 0.05 1.5 0.0 1.0 23266133 46 1.15 2.15 1. 23266133 47 14.3 0.25 0.6 0.95 0.05 0.65 23266133 48 0.8 1.5 2. 23266133 49 14.8 0.75 0.05 1.5 0.05 0.65 23266133 50 0.7 1.75 3. 23266133 51 ENDDATA 10 0 23266133 52 ENDSUBENT 51 0 2326613399999 SUBENT 23266134 20230215 231423266134 1 BIB 5 11 23266134 2 REACTION (62-SM-152(N,G)62-SM-153,,SIG,,AV) 23266134 3 SIG-0 - the average thermal neutron cross-section . 23266134 4 for neutrons at an average energy of E0=25.3 meV 23266134 5 or velocity v0=2200 m/s. 23266134 6 ANALYSIS Derived from directly measured data. 23266134 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266134 8 Uncertainty on exp. SIG-0 value comes from to the 23266134 9 observed SD between gamma-lines. 23266134 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266134 11 (DEP,23266135) Directly measured data. 23266134 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266134 13 ENDBIB 11 0 23266134 14 COMMON 1 3 23266134 15 EN 23266134 16 EV 23266134 17 0.0253 23266134 18 ENDCOMMON 3 0 23266134 19 DATA 2 1 23266134 20 DATA DATA-ERR 23266134 21 B B 23266134 22 207. 1. 23266134 23 ENDDATA 3 0 23266134 24 ENDSUBENT 23 0 2326613499999 SUBENT 23266135 20141210 224123266135 1 BIB 9 26 23266135 2 REACTION (62-SM-152(N,G)62-SM-153,,SIG) 23266135 3 Directly measured thermal neutron cross-section SIG-0 23266135 4 SAMPLE - Provider - IRMM 23266135 5 Matrix - Wire,Al alloy 23266135 6 Elemental content, % weight - 0.008 23266135 7 Average sample thickness, mm - 0.37 23266135 8 (62-SM-152,NAT=0.2675) 26.75+-0.16 % 23266135 9 DECAY-DATA ((1.)62-SM-153,1.9375D,DG,69.7,0.04691) 23266135 10 ((2.)62-SM-153,1.9375D,DG,97.4,0.00779) 23266135 11 ((3.)62-SM-153,1.9375D,DG,103.2,0.2919) reference line 23266135 12 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266135 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266135 14 extrapolated with aid of the k0-definition, atomic 23266135 15 weight, isotopic composition, the gamma intensities 23266135 16 values. 23266135 17 Defined according to their ADS(activation decay scheme,23266135 18 including decay branching factors). 23266135 19 FLAG (4.) Data were measured but were not used in averaging.23266135 20 ADD-RES Measured k0-values with one-sigma uncertainty 23266135 21 E-gamma,keV k0, no-dim.(uncertainty,%) 23266135 22 69.7 3.59E-2 (+-0.8%) 23266135 23 97.4 6.80E-3 (+-1.7%) 23266135 24 103.2 2.25E-1 (+-0.3%) 23266135 25 ERR-ANALYS Uncertainty is not given. 23266135 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266135 27 (COREL,23266134) Average data 23266135 28 ENDBIB 26 0 23266135 29 COMMON 1 3 23266135 30 EN 23266135 31 EV 23266135 32 0.0253 23266135 33 ENDCOMMON 3 0 23266135 34 DATA 3 3 23266135 35 DATA DECAY-FLAG FLAG 23266135 36 B NO-DIM NO-DIM 23266135 37 206. 1. 23266135 38 235. 2. 4. 23266135 39 207. 3. 23266135 40 ENDDATA 5 0 23266135 41 ENDSUBENT 40 0 2326613599999 SUBENT 23266136 20230215 231423266136 1 BIB 8 18 23266136 2 REACTION ((65-TB-159(N,G)65-TB-160,,RI,,AV)// 23266136 3 (65-TB-159(N,G)65-TB-160,,SIG,,AV)) 23266136 4 SAMPLE - Provider - IRMM 23266136 5 Matrix - Ingot,Al alloy 23266136 6 Elemental content, % weight - 1. 23266136 7 Average sample thickness, mm - 3. 23266136 8 (65-TB-159,NAT=1.00) 23266136 9 METHOD Measurement at channel Y4. 23266136 10 DECAY-DATA (65-TB-160,72.3D,DG,86.8,0.132,DG,197.0,0.0518, 23266136 11 DG,215.6,0.0402,DG,298.6,0.2610,DG,879.4,0.3010, 23266136 12 DG,962.3,0.0981,DG,1178.0,0.1490,DG,1199.9,0.0238, 23266136 13 DG,1271.9,0.0744,DG,1312.1,0.0286) 23266136 14 ANALYSIS The Q0 factor was determined by 23266136 15 - the classical method. 23266136 16 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266136 17 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266136 18 (DEP,23266137) Directly measured data . 23266136 19 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266136 20 ENDBIB 18 0 23266136 21 COMMON 2 3 23266136 22 EN-MIN-NM EN-DN 23266136 23 EV EV 23266136 24 0.55 0.0253 23266136 25 ENDCOMMON 3 0 23266136 26 DATA 2 1 23266136 27 DATA DATA-ERR 23266136 28 NO-DIM PER-CENT 23266136 29 18.2 1.5 23266136 30 ENDDATA 3 0 23266136 31 ENDSUBENT 30 0 2326613699999 SUBENT 23266137 20141210 224123266137 1 BIB 7 29 23266137 2 REACTION ((65-TB-159(N,G)65-TB-160,,RI)// 23266137 3 (65-TB-159(N,G)65-TB-160,,SIG)) 23266137 4 Q0 value (ratio of resonance integral to thermal 23266137 5 neutron activation cross-section) 23266137 6 SAMPLE - Provider - IRMM 23266137 7 Matrix - Ingot,Al alloy 23266137 8 Elemental content, % weight - 1. 23266137 9 Average sample thickness, mm - 3. 23266137 10 (65-TB-159,NAT=1.00) 23266137 11 DECAY-DATA (65-TB-160,72.3D,DG,86.8,0.132,DG,197.0,0.0518, 23266137 12 DG,215.6,0.0402,DG,298.6,0.2610,DG,879.4,0.3010, 23266137 13 DG,962.3,0.0981,DG,1178.0,0.1490,DG,1199.9,0.0238, 23266137 14 DG,1271.9,0.0744,DG,1312.1,0.0286) 23266137 15 METHOD Measurement at channel Y4. 23266137 16 ANALYSIS The Q0 factor was determined by the classical method 23266137 17 when inputting effective resonance energy factors 23266137 18 from the literature. 23266137 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266137 20 uncertainties ( 1 sigma) from: 23266137 21 (ERR-1) alpha factor, 23266137 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266137 23 epithermal flux for gold, 23266137 24 (ERR-3) effective resonance energy Er, 23266137 25 (ERR-4) Cd transmission factor FCd 23266137 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266137 27 bare and Cd-covered sample. 23266137 28 (ERR-S) Standard deviation. 23266137 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266137 30 (COREL,23266136) Average data . 23266137 31 ENDBIB 29 0 23266137 32 COMMON 2 3 23266137 33 EN-MIN-NM EN-DN 23266137 34 EV EV 23266137 35 0.55 0.0253 23266137 36 ENDCOMMON 3 0 23266137 37 DATA 8 1 23266137 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266137 39 ERR-5 ERR-SYS 23266137 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266137 41 PER-CENT PER-CENT 23266137 42 18.2 2.0 0.75 1.25 0.1 0.75 23266137 43 0.55 1.75 23266137 44 ENDDATA 6 0 23266137 45 ENDSUBENT 44 0 2326613799999 SUBENT 23266138 20230215 231423266138 1 BIB 5 11 23266138 2 REACTION (65-TB-159(N,G)65-TB-160,,SIG,,AV) 23266138 3 SIG-0 - the average thermal neutron cross-section . 23266138 4 for neutrons at an average energy of E0=25.3 meV 23266138 5 or velocity v0=2200 m/s. 23266138 6 ANALYSIS Derived from directly measured data. 23266138 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266138 8 Uncertainty on exp. SIG-0 value comes from to the 23266138 9 observed SD between gamma-lines. 23266138 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266138 11 (DEP,23266139) Directly measured data. 23266138 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266138 13 ENDBIB 11 0 23266138 14 COMMON 1 3 23266138 15 EN 23266138 16 EV 23266138 17 0.0253 23266138 18 ENDCOMMON 3 0 23266138 19 DATA 2 1 23266138 20 DATA DATA-ERR 23266138 21 B B 23266138 22 23.9 0.2 23266138 23 ENDDATA 3 0 23266138 24 ENDSUBENT 23 0 2326613899999 SUBENT 23266139 20141210 224123266139 1 BIB 8 39 23266139 2 REACTION (65-TB-159(N,G)65-TB-160,,SIG) 23266139 3 Directly measured thermal neutron cross-section SIG-0 23266139 4 SAMPLE - Provider - IRMM 23266139 5 Matrix - Ingot,Al alloy 23266139 6 Elemental content, % weight - 1. 23266139 7 Average sample thickness, mm - 3. 23266139 8 (65-TB-159,NAT=1.00) 23266139 9 DECAY-DATA ((1.)65-TB-160,72.3D,DG,86.8,0.132) 23266139 10 ((2.)65-TB-160,72.3D,DG,197.0,0.0518) 23266139 11 ((3.)65-TB-160,72.3D,DG,215.6,0.0402) 23266139 12 ((4.)65-TB-160,72.3D,DG,298.6,0.2610) 23266139 13 ((5.)65-TB-160,72.3D,DG,879.4,0.3010) 23266139 14 ((6.)65-TB-160,72.3D,DG,962.3,0.0981) 23266139 15 ((7.)65-TB-160,72.3D,DG,1178.0,0.1490) 23266139 16 ((8.)65-TB-160,72.3D,DG,1199.9,0.0238) 23266139 17 ((9.)65-TB-160,72.3D,DG,1271.9,0.0744) 23266139 18 ((10.)65-TB-160,72.3D,DG,1312.1,0.0286) 23266139 19 METHOD Measurement at channels Y4/Cavity. 23266139 20 ANALYSIS An thermal neutron cross-section SIG-0 was 23266139 21 extrapolated with aid of the k0-definition, atomic 23266139 22 weight, isotopic composition, the gamma intensities 23266139 23 values. 23266139 24 Defined according to their ADS(activation decay scheme,23266139 25 including decay branching factors). 23266139 26 ADD-RES Measured k0-values with one-sigma uncertainty 23266139 27 E-gamma,keV k0, no-dim.(uncertainty,%) 23266139 28 86.8 4.18E-2 (+-0.6%) 23266139 29 197.0 1.62E-2 (+-1.0%) 23266139 30 215.6 1.28E-2 (+-0.7%) 23266139 31 298.6 8.26E-2 (+-0.8%) 23266139 32 879.4 9.45E-2 (+-0.7%) 23266139 33 962.3 3.05E-2 (+-0.7%) 23266139 34 1178.0 4.71E-2 (+-0.6%) 23266139 35 1199.9 7.43E-3 (+-0.8%) 23266139 36 1271.9 2.36E-2 (+-0.7%) 23266139 37 1312.1 8.97E-3 (+-0.7%) 23266139 38 ERR-ANALYS Uncertainty is not given. 23266139 39 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266139 40 (COREL,23266138) Average data 23266139 41 ENDBIB 39 0 23266139 42 COMMON 1 3 23266139 43 EN 23266139 44 EV 23266139 45 0.0253 23266139 46 ENDCOMMON 3 0 23266139 47 DATA 2 10 23266139 48 DATA DECAY-FLAG 23266139 49 B NO-DIM 23266139 50 24.1 1. 23266139 51 23.8 2. 23266139 52 24.2 3. 23266139 53 24.1 4. 23266139 54 23.9 5. 23266139 55 23.6 6. 23266139 56 24.0 7. 23266139 57 23.7 8. 23266139 58 24.1 9. 23266139 59 23.9 10. 23266139 60 ENDDATA 12 0 23266139 61 ENDSUBENT 60 0 2326613999999 SUBENT 23266140 20230215 231423266140 1 BIB 8 26 23266140 2 REACTION 1((67-HO-165(N,G)67-HO-166,,RI,,AV)// 23266140 3 (67-HO-165(N,G)67-HO-166,,SIG,,AV)) 23266140 4 2((67-HO-165(N,G)67-HO-166,,RI)// 23266140 5 (67-HO-165(N,G)67-HO-166,,SIG)) 23266140 6 Q0 value (ratio of resonance integral to thermal 23266140 7 neutron activation cross-section) 23266140 8 SAMPLE - Provider - IRMM 23266140 9 Matrix - Foil,Al alloy 23266140 10 Elemental content, % weight - 5. 23266140 11 Average sample thickness, mm - 0.1 23266140 12 (67-HO-165,NAT=1.00) 23266140 13 METHOD Measurement at channels S84, Y4, X26 . 23266140 14 DECAY-DATA (67-HO-166-G,26.83HR,DG,80.6,0.0656,DG,1379.4,0.0092, 23266140 15 DG,1581.9,0.0018,DG,1662.5,0.0012) 23266140 16 ANALYSIS The Q0 factor was determined by 23266140 17 1- the classical method: through the weighted mean and 23266140 18 observed standard deviation of the 3 irradiation 23266140 19 channels employed (Y4, S84, X26), when inputting Er 23266140 20 factors from the literature. 23266140 21 2- the a-vector method: through the parameters 23266140 22 (m, b) --> determination of the value as well. 23266140 23 ADD-RES Effective resonance Energy was defined by a-vect23266140 24 method to be 15.2 eV ( +-11%, 2sigma). 23266140 25 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266140 26 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266140 27 1(DEP,23266141) Directly measured data . 23266140 28 ENDBIB 26 0 23266140 29 COMMON 2 3 23266140 30 EN-MIN-NM EN-DN 23266140 31 EV EV 23266140 32 0.55 0.0253 23266140 33 ENDCOMMON 3 0 23266140 34 DATA 4 1 23266140 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266140 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266140 37 11.2 2.5 11.3 2. 23266140 38 ENDDATA 3 0 23266140 39 ENDSUBENT 38 0 2326614099999 SUBENT 23266141 20141210 224123266141 1 BIB 7 30 23266141 2 REACTION ((67-HO-165(N,G)67-HO-166,,RI)// 23266141 3 (67-HO-165(N,G)67-HO-166,,SIG)) 23266141 4 Q0 value (ratio of resonance integral to thermal 23266141 5 neutron activation cross-section) 23266141 6 SAMPLE - Provider - IRMM 23266141 7 Matrix - Foil,Al alloy 23266141 8 Elemental content, % weight - 5. 23266141 9 Average sample thickness, mm - 0.1 23266141 10 (67-HO-165,NAT=1.00) 23266141 11 DECAY-DATA (67-HO-166-G,26.83HR,DG,80.6,0.0656,DG,1379.4,0.0092, 23266141 12 DG,1581.9,0.0018,DG,1662.5,0.0012) 23266141 13 FLAG Measurement at channels 23266141 14 (1.) S84, 23266141 15 (2.) Y4, 23266141 16 (3.) X26 23266141 17 ANALYSIS The Q0 factor was determined by the classical method 23266141 18 when inputting effective resonance energy factors 23266141 19 from the literature. 23266141 20 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266141 21 uncertainties ( 1 sigma) from: 23266141 22 (ERR-1) alpha factor, 23266141 23 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266141 24 epithermal flux for gold, 23266141 25 (ERR-3) effective resonance energy Er, 23266141 26 (ERR-4) Cd transmission factor FCd, 23266141 27 (ERR-5) A/ACd -ratio of induced gamma activities, 23266141 28 bare and Cd-covered sample. 23266141 29 (ERR-S) Standard deviation. 23266141 30 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266141 31 (COREL,23266140) Average data . 23266141 32 ENDBIB 30 0 23266141 33 COMMON 2 3 23266141 34 EN-MIN-NM EN-DN 23266141 35 EV EV 23266141 36 0.55 0.0253 23266141 37 ENDCOMMON 3 0 23266141 38 DATA 9 3 23266141 39 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266141 40 ERR-5 ERR-SYS FLAG 23266141 41 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266141 42 PER-CENT PER-CENT NO-DIM 23266141 43 11.5 1.1 0.7 1.5 0.0 2.0 23266141 44 1.2 2.85 1. 23266141 45 10.8 0.55 0.15 1.4 0.0 1.5 23266141 46 0.65 2.15 2. 23266141 47 11.3 0.75 0.6 1.35 0.1 1.2 23266141 48 0.6 2.0 3. 23266141 49 ENDDATA 10 0 23266141 50 ENDSUBENT 49 0 2326614199999 SUBENT 23266142 20230215 231423266142 1 BIB 5 11 23266142 2 REACTION (67-HO-165(N,G)67-HO-166,,SIG,,AV) 23266142 3 SIG-0 - the average thermal neutron cross-section . 23266142 4 for neutrons at an average energy of E0=25.3 meV 23266142 5 or velocity v0=2200 m/s. 23266142 6 ANALYSIS Derived from directly measured data. 23266142 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266142 8 Uncertainty on exp. SIG-0 value comes from to the 23266142 9 observed SD between gamma-lines. 23266142 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266142 11 (DEP,23266143) Directly measured data. 23266142 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266142 13 ENDBIB 11 0 23266142 14 COMMON 1 3 23266142 15 EN 23266142 16 EV 23266142 17 0.0253 23266142 18 ENDCOMMON 3 0 23266142 19 DATA 2 1 23266142 20 DATA DATA-ERR 23266142 21 B B 23266142 22 60.9 0.8 23266142 23 ENDDATA 3 0 23266142 24 ENDSUBENT 23 0 2326614299999 SUBENT 23266143 20141210 224123266143 1 BIB 8 27 23266143 2 REACTION (67-HO-165(N,G)67-HO-166,,SIG) 23266143 3 Directly measured thermal neutron cross-section SIG-0 23266143 4 SAMPLE - Provider - IRMM 23266143 5 Matrix - Foil,Al alloy 23266143 6 Elemental content, % weight - 5. 23266143 7 Average sample thickness, mm - 0.1 23266143 8 (67-HO-165,NAT=1.00) 23266143 9 DECAY-DATA ((1.)67-HO-166-G,26.83HR,DG,80.6,0.0656) reference line23266143 10 ((2.)67-HO-166-G,26.83HR,DG,1379.4,0.0092) 23266143 11 ((3.)67-HO-166-G,26.83HR,DG,1581.9,0.0018) 23266143 12 ((4.)67-HO-166-G,26.83HR,DG,1662.5,0.0012) 23266143 13 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266143 14 ANALYSIS An thermal neutron cross-section SIG-0 was 23266143 15 extrapolated with aid of the k0-definition, atomic 23266143 16 weight, isotopic composition, the gamma intensities 23266143 17 values. 23266143 18 Defined according to their ADS(activation decay scheme,23266143 19 including decay branching factors). 23266143 20 ADD-RES Measured k0-values with one-sigma uncertainty 23266143 21 E-gamma,keV k0, no-dim.(uncertainty,%) 23266143 22 80.6 5.13E-2 (+-0.7%) 23266143 23 1379.4 7.06E-3 (+-0.4%) 23266143 24 1581.9 1.41E-3 (+-0.8%) 23266143 25 1662.5 9.06e-4 (+-1.3%) 23266143 26 ERR-ANALYS Uncertainty is not given. 23266143 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266143 28 (COREL,23266142) Average data 23266143 29 ENDBIB 27 0 23266143 30 COMMON 1 3 23266143 31 EN 23266143 32 EV 23266143 33 0.0253 23266143 34 ENDCOMMON 3 0 23266143 35 DATA 2 4 23266143 36 DATA DECAY-FLAG 23266143 37 B NO-DIM 23266143 38 61.7 1. 23266143 39 60.4 2. 23266143 40 61.3 3. 23266143 41 60.0 4. 23266143 42 ENDDATA 6 0 23266143 43 ENDSUBENT 42 0 2326614399999 SUBENT 23266144 20230215 231423266144 1 BIB 9 26 23266144 2 REACTION 1((75-RE-185(N,G)75-RE-186,,RI,,AV)// 23266144 3 (75-RE-185(N,G)75-RE-186,,SIG,,AV)) 23266144 4 2((75-RE-185(N,G)75-RE-186,,RI)// 23266144 5 (75-RE-185(N,G)75-RE-186,,SIG)) 23266144 6 Q0 value (ratio of resonance integral to thermal 23266144 7 neutron activation cross-section) 23266144 8 SAMPLE - Provider - IRMM 23266144 9 Matrix - Wire,Al alloy 23266144 10 Elemental content, % weight - 0.118 23266144 11 Average sample thickness, mm - 1. 23266144 12 (75-RE-185,NAT=0.3740) 37.40+-0.02 % 23266144 13 METHOD Measurement at channels S84, Y4, X26 . 23266144 14 DECAY-DATA (75-RE-186-G,3.718D,DG,122.6,0.00603,DG,137.2,0.09420) 23266144 15 ANALYSIS The Q0 factor was determined by 23266144 16 1- the classical method: through the weighted mean and 23266144 17 observed standard deviation of the 3 irradiation 23266144 18 channels employed (Y4, S84, X26), when inputting Er 23266144 19 factors from the literature. 23266144 20 2- the a-vector method: through the parameters 23266144 21 (m, b) --> determination of the value as well. 23266144 22 ADD-RES Effective resonance Energy was defined by a-vect23266144 23 method to be 3.55 eV ( +-3%, 2sigma). 23266144 24 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266144 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266144 26 1(DEP,23266145) Directly measured data . 23266144 27 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266144 28 ENDBIB 26 0 23266144 29 COMMON 2 3 23266144 30 EN-MIN-NM EN-DN 23266144 31 EV EV 23266144 32 0.55 0.0253 23266144 33 ENDCOMMON 3 0 23266144 34 DATA 4 1 23266144 35 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266144 36 NO-DIM PER-CENT NO-DIM PER-CENT 23266144 37 14.6 0.5 14.6 2.5 23266144 38 ENDDATA 3 0 23266144 39 ENDSUBENT 38 0 2326614499999 SUBENT 23266145 20141210 224123266145 1 BIB 7 29 23266145 2 REACTION ((75-RE-185(N,G)75-RE-186,,RI)// 23266145 3 (75-RE-185(N,G)75-RE-186,,SIG)) 23266145 4 Q0 value (ratio of resonance integral to thermal 23266145 5 neutron activation cross-section) 23266145 6 SAMPLE - Provider - IRMM 23266145 7 Matrix - Wire,Al alloy 23266145 8 Elemental content, % weight - 0.118 23266145 9 Average sample thickness, mm - 1. 23266145 10 (75-RE-185,NAT=0.3740) 37.40+-0.02 % 23266145 11 DECAY-DATA (75-RE-186-G,3.718D,DG,122.6,0.00603,DG,137.2,0.09420) 23266145 12 FLAG Measurement at channels 23266145 13 (1.) S84, 23266145 14 (2.) Y4, 23266145 15 (3.) X26 23266145 16 ANALYSIS The Q0 factor was determined by the classical method 23266145 17 when inputting effective resonance energy factors 23266145 18 from the literature. 23266145 19 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266145 20 uncertainties ( 1 sigma) from: 23266145 21 (ERR-1) alpha factor, 23266145 22 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266145 23 epithermal flux for gold, 23266145 24 (ERR-3) effective resonance energy Er, 23266145 25 (ERR-4) Cd transmission factor FCd, 23266145 26 (ERR-5) A/ACd -ratio of induced gamma activities, 23266145 27 bare and Cd-covered sample. 23266145 28 (ERR-S) Standard deviation. 23266145 29 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266145 30 (COREL,23266144) Average data . 23266145 31 ENDBIB 29 0 23266145 32 COMMON 2 3 23266145 33 EN-MIN-NM EN-DN 23266145 34 EV EV 23266145 35 0.55 0.0253 23266145 36 ENDCOMMON 3 0 23266145 37 DATA 9 3 23266145 38 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266145 39 ERR-5 ERR-SYS FLAG 23266145 40 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266145 41 PER-CENT PER-CENT NO-DIM 23266145 42 14.6 1.0 0.85 1.5 0.0 1.95 23266145 43 1.15 2.85 1. 23266145 44 14.6 0.65 0.75 1.3 0.1 1.4 23266145 45 0.8 2.2 2. 23266145 46 14.5 0.45 0.4 1.3 0.2 1.15 23266145 47 0.7 1.9 3. 23266145 48 ENDDATA 10 0 23266145 49 ENDSUBENT 48 0 2326614599999 SUBENT 23266146 20230215 231423266146 1 BIB 5 11 23266146 2 REACTION (75-RE-185(N,G)75-RE-186,,SIG,,AV) 23266146 3 SIG-0 - the average thermal neutron cross-section . 23266146 4 for neutrons at an average energy of E0=25.3 meV 23266146 5 or velocity v0=2200 m/s. 23266146 6 ANALYSIS Derived from directly measured data. 23266146 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266146 8 Uncertainty on exp. SIG-0 value comes from to the 23266146 9 observed SD between gamma-lines. 23266146 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266146 11 (DEP,23266147) Directly measured data. 23266146 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266146 13 ENDBIB 11 0 23266146 14 COMMON 1 3 23266146 15 EN 23266146 16 EV 23266146 17 0.0253 23266146 18 ENDCOMMON 3 0 23266146 19 DATA 2 1 23266146 20 DATA DATA-ERR 23266146 21 B B 23266146 22 111.6 1.1 23266146 23 ENDDATA 3 0 23266146 24 ENDSUBENT 23 0 2326614699999 SUBENT 23266147 20141210 224123266147 1 BIB 8 24 23266147 2 REACTION (75-RE-185(N,G)75-RE-186,,SIG) 23266147 3 Directly measured thermal neutron cross-section SIG-0 23266147 4 SAMPLE - Provider - IRMM 23266147 5 Matrix - Wire,Al alloy 23266147 6 Elemental content, % weight - 0.118 23266147 7 Average sample thickness, mm - 1. 23266147 8 (75-RE-185,NAT=0.3740) 37.40+-0.02 % 23266147 9 DECAY-DATA ((1.)75-RE-186-G,3.718D,DG,122.6,0.00603) 23266147 10 ((2.)75-RE-186-G,3.718D,DG,137.2,0.09420) 23266147 11 reference line 23266147 12 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266147 13 ANALYSIS An thermal neutron cross-section SIG-0 was 23266147 14 extrapolated with aid of the k0-definition, atomic 23266147 15 weight, isotopic composition, the gamma intensities 23266147 16 values. 23266147 17 Defined according to their ADS(activation decay scheme,23266147 18 including decay branching factors). 23266147 19 ADD-RES Measured k0-values with one-sigma uncertainty 23266147 20 E-gamma,keV k0, no-dim.(uncertainty,%) 23266147 21 122.6 2.83E-3 (+-0.3%) 23266147 22 137.24 4.48E-2 (+-0.2%) 23266147 23 ERR-ANALYS Uncertainty is not given. 23266147 24 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266147 25 (COREL,23266146) Average data 23266147 26 ENDBIB 24 0 23266147 27 COMMON 1 3 23266147 28 EN 23266147 29 EV 23266147 30 0.0253 23266147 31 ENDCOMMON 3 0 23266147 32 DATA 2 2 23266147 33 DATA DECAY-FLAG 23266147 34 B NO-DIM 23266147 35 110.9 1. 23266147 36 112.4 2. 23266147 37 ENDDATA 4 0 23266147 38 ENDSUBENT 37 0 2326614799999 SUBENT 23266148 20230215 231423266148 1 BIB 8 17 23266148 2 REACTION ((75-RE-187(N,G)75-RE-188-M,,RI,,AV)// 23266148 3 (75-RE-187(N,G)75-RE-188-M,,SIG,,AV)) 23266148 4 SAMPLE - Provider - IRMM 23266148 5 Matrix - Wire,Al alloy 23266148 6 Elemental content, % weight - 0.118 23266148 7 Average sample thickness, mm - 1. 23266148 8 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266148 9 METHOD Measurement at channel S84. 23266148 10 DECAY-DATA (75-RE-188-M,18.59MIN,DG,92.4,0.051,DG,106.0,0.108) 23266148 11 18.59+-0.04 min. 23266148 12 (75-RE-188-G,17.01HR) 23266148 13 ANALYSIS The Q0 factor was determined by 23266148 14 - the classical method. 23266148 15 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266148 16 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266148 17 (DEP,23266149) Directly measured data . 23266148 18 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266148 19 ENDBIB 17 0 23266148 20 COMMON 2 3 23266148 21 EN-MIN-NM EN-DN 23266148 22 EV EV 23266148 23 0.55 0.0253 23266148 24 ENDCOMMON 3 0 23266148 25 DATA 2 1 23266148 26 DATA DATA-ERR 23266148 27 NO-DIM PER-CENT 23266148 28 4.54 1. 23266148 29 ENDDATA 3 0 23266148 30 ENDSUBENT 29 0 2326614899999 SUBENT 23266149 20141210 224123266149 1 BIB 7 28 23266149 2 REACTION ((75-RE-187(N,G)75-RE-188-M,,RI)// 23266149 3 (75-RE-187(N,G)75-RE-188-M,,SIG)) 23266149 4 Q0 value (ratio of resonance integral to thermal 23266149 5 neutron activation cross-section) 23266149 6 SAMPLE - Provider - IRMM 23266149 7 Matrix - Wire,Al alloy 23266149 8 Elemental content, % weight - 0.118 23266149 9 Average sample thickness, mm - 1. 23266149 10 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266149 11 DECAY-DATA (75-RE-188-M,18.59MIN,DG,92.4,0.051,DG,106.0,0.108) 23266149 12 18.59+-0.04 min. 23266149 13 (75-RE-188-G,17.01HR) 23266149 14 METHOD Measurement at channel S84. 23266149 15 ANALYSIS The Q0 factor was determined by the classical method 23266149 16 when inputting effective resonance energy factors 23266149 17 from the literature. 23266149 18 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266149 19 uncertainties ( 1 sigma) from: 23266149 20 (ERR-1) alpha factor, 23266149 21 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266149 22 epithermal flux for gold, 23266149 23 (ERR-3) effective resonance energy Er, 23266149 24 (ERR-4) Cd transmission factor FCd 23266149 25 (ERR-5) A/ACd -ratio of induced gamma activities, 23266149 26 bare and Cd-covered sample. 23266149 27 (ERR-S) Standard deviation. 23266149 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266149 29 (COREL,23266148) Average data . 23266149 30 ENDBIB 28 0 23266149 31 COMMON 2 3 23266149 32 EN-MIN-NM EN-DN 23266149 33 EV EV 23266149 34 0.55 0.0253 23266149 35 ENDCOMMON 3 0 23266149 36 DATA 8 1 23266149 37 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266149 38 ERR-5 ERR-SYS 23266149 39 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266149 40 PER-CENT PER-CENT 23266149 41 4.54 3.0 0.55 1.5 0.0 0.65 23266149 42 0.75 1.9 23266149 43 ENDDATA 6 0 23266149 44 ENDSUBENT 43 0 2326614999999 SUBENT 23266150 20230215 231423266150 1 BIB 5 11 23266150 2 REACTION (75-RE-187(N,G)75-RE-188-M,,SIG,,AV) 23266150 3 SIG-0 - the average thermal neutron cross-section . 23266150 4 for neutrons at an average energy of E0=25.3 meV 23266150 5 or velocity v0=2200 m/s. 23266150 6 ANALYSIS Derived from directly measured data. 23266150 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266150 8 Uncertainty on exp. SIG-0 value comes from to the 23266150 9 observed SD between gamma-lines. 23266150 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266150 11 (DEP,23266151) Directly measured data. 23266150 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266150 13 ENDBIB 11 0 23266150 14 COMMON 1 3 23266150 15 EN 23266150 16 EV 23266150 17 0.0253 23266150 18 ENDCOMMON 3 0 23266150 19 DATA 2 1 23266150 20 DATA DATA-ERR 23266150 21 B B 23266150 22 2.06 0.03 23266150 23 ENDDATA 3 0 23266150 24 ENDSUBENT 23 0 2326615099999 SUBENT 23266151 20141210 224123266151 1 BIB 8 25 23266151 2 REACTION (75-RE-187(N,G)75-RE-188-M,,SIG) 23266151 3 Directly measured thermal neutron cross-section SIG-0 23266151 4 SAMPLE - Provider - IRMM 23266151 5 Matrix - Wire,Al alloy 23266151 6 Elemental content, % weight - 0.118 23266151 7 Average sample thickness, mm - 1. 23266151 8 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266151 9 DECAY-DATA ((1.)75-RE-188-M,18.59MIN,DG,92.4,0.051) 23266151 10 ((2.)75-RE-188-M,18.59MIN,DG,106.0,0.108)reference line23266151 11 18.59+-0.04 min. 23266151 12 (75-RE-188-G,17.01HR) 23266151 13 METHOD Measurement at channel S84 . 23266151 14 ANALYSIS An thermal neutron cross-section SIG-0 was 23266151 15 extrapolated with aid of the k0-definition, atomic 23266151 16 weight, isotopic composition, the gamma intensities 23266151 17 values. 23266151 18 Defined according to their ADS(activation decay scheme,23266151 19 including decay branching factors). 23266151 20 ADD-RES Measured k0-values with one-sigma uncertainty 23266151 21 E-gamma,keV k0, no-dim.(uncertainty,%) 23266151 22 92.4 7.43E-4 (+-1.2%) 23266151 23 106.04 1.54E-3 (+-1.5%) 23266151 24 ERR-ANALYS Uncertainty is not given. 23266151 25 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266151 26 (COREL,23266150) Average data 23266151 27 ENDBIB 25 0 23266151 28 COMMON 1 3 23266151 29 EN 23266151 30 EV 23266151 31 0.0253 23266151 32 ENDCOMMON 3 0 23266151 33 DATA 2 2 23266151 34 DATA DECAY-FLAG 23266151 35 B NO-DIM 23266151 36 2.09 1. 23266151 37 2.04 2. 23266151 38 ENDDATA 4 0 23266151 39 ENDSUBENT 38 0 2326615199999 SUBENT 23266152 20230215 231423266152 1 BIB 9 28 23266152 2 REACTION 1((75-RE-187(N,G)75-RE-188,,RI,,AV)// 23266152 3 (75-RE-187(N,G)75-RE-188,,SIG,,AV)) 23266152 4 2((75-RE-187(N,G)75-RE-188,,RI)// 23266152 5 (75-RE-187(N,G)75-RE-188,,SIG)) 23266152 6 Q0 value (ratio of resonance integral to thermal 23266152 7 neutron activation cross-section) 23266152 8 SAMPLE - Provider - IRMM 23266152 9 Matrix - Wire,Al alloy 23266152 10 Elemental content, % weight - 0.118 23266152 11 Average sample thickness, mm - 1. 23266152 12 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266152 13 METHOD Measurement at channels S84, Y4, X26 . 23266152 14 DECAY-DATA (75-RE-188-G,17.01HR,DG,155.0,0.1520,DG,478.0,0.0102, 23266152 15 DG,633.0,0.0128,DG,635.0,0.00148,DG,829.5,0.0041, 23266152 16 DG,931.3,0.0055) 23266152 17 ANALYSIS The Q0 factor was determined by 23266152 18 1- the classical method: through the weighted mean and 23266152 19 observed standard deviation of the 3 irradiation 23266152 20 channels employed (Y4, S84, X26), when inputting Er 23266152 21 factors from the literature. 23266152 22 2- the a-vector method: through the parameters 23266152 23 (m, b) --> determination of the value as well. 23266152 24 ADD-RES Effective resonance Energy was defined by a-vect23266152 25 method to be 70.2 eV ( +-3%, 2sigma). 23266152 26 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266152 27 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266152 28 1(DEP,23266154) Directly measured data . 23266152 29 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266152 30 ENDBIB 28 0 23266152 31 COMMON 2 3 23266152 32 EN-MIN-NM EN-DN 23266152 33 EV EV 23266152 34 0.55 0.0253 23266152 35 ENDCOMMON 3 0 23266152 36 DATA 4 1 23266152 37 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266152 38 NO-DIM PER-CENT NO-DIM PER-CENT 23266152 39 4.19 2.5 4.33 2. 23266152 40 ENDDATA 3 0 23266152 41 ENDSUBENT 40 0 2326615299999 SUBENT 23266153 20141210 224123266153 1 BIB 7 27 23266153 2 REACTION 1((75-RE-187(N,G)75-RE-188,,RI)// 23266153 3 (75-RE-187(N,G)75-RE-188,,SIG)) 23266153 4 2((75-RE-187(N,G)75-RE-188,,RI)// 23266153 5 (75-RE-187(N,G)75-RE-188,,SIG)) 23266153 6 Q0 value (ratio of resonance integral to thermal 23266153 7 neutron activation cross-section) 23266153 8 SAMPLE - Provider - IRMM 23266153 9 Matrix - Wire,Al alloy 23266153 10 Elemental content, % weight - 0.118 23266153 11 Average sample thickness, mm - 1. 23266153 12 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266153 13 METHOD Measurement at channels S84, Y4, X26 . 23266153 14 DECAY-DATA (75-RE-188-G,17.01HR,DG,155.0,0.1520,DG,478.0,0.0102, 23266153 15 DG,633.0,0.0128,DG,635.0,0.00148,DG,829.5,0.0041, 23266153 16 DG,931.3,0.0055) 23266153 17 (75-RE-188-M,18.59MIN,DG,92.4,0.051,DG,106.0,0.108) 23266153 18 18.59+-0.04 min. 23266153 19 ANALYSIS The Q0 factor was calculated from Re-188 (ADS IV/B) and23266153 20 Re-188m ( ADS I) results by 23266153 21 1- the classical method: through the weighted mean and 23266153 22 observed standard deviation of the 3 irradiation 23266153 23 channels employed (Y4, S84, X26), when inputting Er 23266153 24 factors from the literature. 23266153 25 2- the a-vector method: through the parameters 23266153 26 (m, b) --> determination of the value as well. 23266153 27 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266153 28 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266153 29 ENDBIB 27 0 23266153 30 COMMON 2 3 23266153 31 EN-MIN-NM EN-DN 23266153 32 EV EV 23266153 33 0.55 0.0253 23266153 34 ENDCOMMON 3 0 23266153 35 DATA 4 1 23266153 36 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266153 37 NO-DIM PER-CENT NO-DIM PER-CENT 23266153 38 4.18 2.5 4.32 2. 23266153 39 ENDDATA 3 0 23266153 40 ENDSUBENT 39 0 2326615399999 SUBENT 23266154 20141210 224123266154 1 BIB 7 31 23266154 2 REACTION ((75-RE-187(N,G)75-RE-188,,RI)// 23266154 3 (75-RE-187(N,G)75-RE-188,,SIG)) 23266154 4 Q0 value (ratio of resonance integral to thermal 23266154 5 neutron activation cross-section) 23266154 6 SAMPLE - Provider - IRMM 23266154 7 Matrix - Wire,Al alloy 23266154 8 Elemental content, % weight - 0.118 23266154 9 Average sample thickness, mm - 1. 23266154 10 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266154 11 DECAY-DATA (75-RE-188-G,17.01HR,DG,155.0,0.1520,DG,478.0,0.0102, 23266154 12 DG,633.0,0.0128,DG,635.0,0.00148,DG,829.5,0.0041, 23266154 13 DG,931.3,0.0055) 23266154 14 FLAG Measurement at channels 23266154 15 (1.) S84, 23266154 16 (2.) Y4, 23266154 17 (3.) X26 23266154 18 ANALYSIS The Q0 factor was determined by the classical method 23266154 19 when inputting effective resonance energy factors 23266154 20 from the literature. 23266154 21 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266154 22 uncertainties ( 1 sigma) from: 23266154 23 (ERR-1) alpha factor, 23266154 24 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266154 25 epithermal flux for gold, 23266154 26 (ERR-3) effective resonance energy Er, 23266154 27 (ERR-4) Cd transmission factor FCd 23266154 28 (ERR-5) A/ACd -ratio of induced gamma activities, 23266154 29 bare and Cd-covered sample. 23266154 30 (ERR-S) Standard deviation. 23266154 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266154 32 (COREL,23266152) Average data . 23266154 33 ENDBIB 31 0 23266154 34 COMMON 2 3 23266154 35 EN-MIN-NM EN-DN 23266154 36 EV EV 23266154 37 0.55 0.0253 23266154 38 ENDCOMMON 3 0 23266154 39 DATA 9 3 23266154 40 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266154 41 ERR-5 ERR-SYS FLAG 23266154 42 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266154 43 PER-CENT PER-CENT NO-DIM 23266154 44 4.34 0.8 0.55 1.5 0.0 0.65 23266154 45 0.75 1.9 1. 23266154 46 4.17 0.85 0.15 1.3 0.1 0.55 23266154 47 0.65 1.6 2. 23266154 48 4.07 1.0 1.05 1.35 0.2 0.55 23266154 49 0.65 1.9 3. 23266154 50 ENDDATA 10 0 23266154 51 ENDSUBENT 50 0 2326615499999 SUBENT 23266155 20230215 231423266155 1 BIB 5 12 23266155 2 REACTION (75-RE-187(N,G)75-RE-188,,SIG,,AV) 23266155 3 SIG-0 - the average thermal neutron cross-section . 23266155 4 for neutrons at an average energy of E0=25.3 meV 23266155 5 or velocity v0=2200 m/s. 23266155 6 ANALYSIS Derived from directly measured data. 23266155 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266155 8 Uncertainty on exp. SIG-0 value comes from to the 23266155 9 observed SD between gamma-lines. 23266155 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266155 11 (DEP,23266156) Directly measured data at S84 only. 23266155 12 (DEP,23266157) Directly measure data at all channels. 23266155 13 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266155 14 ENDBIB 12 0 23266155 15 COMMON 1 3 23266155 16 EN 23266155 17 EV 23266155 18 0.0253 23266155 19 ENDCOMMON 3 0 23266155 20 DATA 2 1 23266155 21 DATA DATA-ERR 23266155 22 B B 23266155 23 74.6 1.4 23266155 24 ENDDATA 3 0 23266155 25 ENDSUBENT 24 0 2326615599999 SUBENT 23266156 20141210 224123266156 1 BIB 9 33 23266156 2 REACTION (75-RE-187(N,G)75-RE-188,,SIG) 23266156 3 Directly measured thermal neutron cross-section SIG-0 23266156 4 SAMPLE - Provider - IRMM 23266156 5 Matrix - Wire,Al alloy 23266156 6 Elemental content, % weight - 0.118 23266156 7 Average sample thickness, mm - 1. 23266156 8 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266156 9 DECAY-DATA ((1.)75-RE-188-G,17.01HR,DG,155.0,0.1520) 23266156 10 reference line . 23266156 11 ((2.)75-RE-188-G,17.01HR,DG,478.0,0.0102) 23266156 12 ((3.)75-RE-188-G,17.01HR,DG,633.0,0.0128) 23266156 13 ((4.)75-RE-188-G,17.01HR,DG,635.0,0.00148) 23266156 14 ((5.)75-RE-188-G,17.01HR,DG,829.5,0.0041) 23266156 15 ((6.)75-RE-188-G,17.01HR,DG,931.3,0.0055) 23266156 16 METHOD Measurement at channel S84. 23266156 17 ANALYSIS An thermal neutron cross-section SIG-0 was 23266156 18 extrapolated with aid of the k0-definition, atomic 23266156 19 weight, isotopic composition, the gamma intensities 23266156 20 values. 23266156 21 Defined according to their ADS(activation decay scheme,23266156 22 including decay branching factors). 23266156 23 FLAG (7.) Data were measured but were not used in averaging.23266156 24 ADD-RES Measured k0-values with one-sigma uncertainty 23266156 25 E-gamma,keV k0, no-dim.(uncertainty,%) 23266156 26 155.0 7.79E-2 (+-0.8%) 23266156 27 478.0 5.29E-3 (+-1.3%) 23266156 28 633.0 6.81E-3 (+-1.6%) 23266156 29 635.0 8.10E-4 23266156 30 829.5 2.22E-3 23266156 31 931.3 2.91E-3 23266156 32 ERR-ANALYS Uncertainty is not given. 23266156 33 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266156 34 (COREL,23266155) Average data 23266156 35 ENDBIB 33 0 23266156 36 COMMON 1 3 23266156 37 EN 23266156 38 EV 23266156 39 0.0253 23266156 40 ENDCOMMON 3 0 23266156 41 DATA 3 6 23266156 42 DATA DECAY-FLAG FLAG 23266156 43 B NO-DIM NO-DIM 23266156 44 73.4 1. 23266156 45 74.2 2. 23266156 46 76.2 3. 23266156 47 78.4 4. 7. 23266156 48 77.6 5. 7. 23266156 49 75.9 6. 7. 23266156 50 ENDDATA 8 0 23266156 51 ENDSUBENT 50 0 2326615699999 SUBENT 23266157 20141210 224123266157 1 BIB 8 31 23266157 2 REACTION (75-RE-187(N,G)75-RE-188,,SIG) 23266157 3 Directly measured thermal neutron cross-section SIG-0 23266157 4 SAMPLE - Provider - IRMM 23266157 5 Matrix - Wire,Al alloy 23266157 6 Elemental content, % weight - 0.118 23266157 7 Average sample thickness, mm - 1. 23266157 8 (75-RE-187,NAT=0.6260) 62.60+-0.02 % 23266157 9 DECAY-DATA ((1.)75-RE-188-G,17.01HR,DG,155.0,0.1520)reference line23266157 10 ((2.)75-RE-188-G,17.01HR,DG,478.0,0.0102) 23266157 11 ((3.)75-RE-188-G,17.01HR,DG,633.0,0.0128) 23266157 12 ((4.)75-RE-188-G,17.01HR,DG,635.0,0.00148) 23266157 13 ((5.)75-RE-188-G,17.01HR,DG,829.5,0.0041) 23266157 14 ((6.)75-RE-188-G,17.01HR,DG,931.3,0.0055) 23266157 15 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266157 16 ANALYSIS An thermal neutron cross-section SIG-0 was 23266157 17 extrapolated with aid of the k0-definition, atomic 23266157 18 weight, isotopic composition, the gamma intensities 23266157 19 values. 23266157 20 Defined according to their ADS(activation decay scheme,23266157 21 including decay branching factors). 23266157 22 ADD-RES Measured k0-values with one-sigma uncertainty 23266157 23 E-gamma,keV k0, no-dim.(uncertainty,%) 23266157 24 155.0 8.01E-2 (+-1.4%) 23266157 25 478.0 5.43E-3 (+-0.7%) 23266157 26 633.0 6.99E-3 (+-1.5%) 23266157 27 635.0 8.32E-4 (+-2.0%) 23266157 28 829.5 2.28E-3 (+-1.1%) 23266157 29 931.3 2.99E-3 (+-1.0%) 23266157 30 ERR-ANALYS Uncertainty is not given. 23266157 31 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266157 32 (COREL,23266155) Average data 23266157 33 ENDBIB 31 0 23266157 34 COMMON 1 3 23266157 35 EN 23266157 36 EV 23266157 37 0.0253 23266157 38 ENDCOMMON 3 0 23266157 39 DATA 2 6 23266157 40 DATA DECAY-FLAG 23266157 41 B NO-DIM 23266157 42 73.4 1. 23266157 43 74.2 2. 23266157 44 76.1 3. 23266157 45 78.3 4. 23266157 46 77.6 5. 23266157 47 75.9 6. 23266157 48 ENDDATA 8 0 23266157 49 ENDSUBENT 48 0 2326615799999 SUBENT 23266158 20141210 224123266158 1 BIB 5 10 23266158 2 REACTION (75-RE-187(N,G)75-RE-188-M/G,,SIG/RAT,,,DERIV) 23266158 3 Isomeric ratio M/G. 23266158 4 DECAY-DATA (75-RE-188-G,17.01HR) 23266158 5 (75-RE-188-M,18.59MIN) 23266158 6 18.59+-0.04 min. 23266158 7 ANALYSIS Derived from measured cross sections.. 23266158 8 ERR-ANALYS Uncertainty not given. 23266158 9 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266158 10 (DEP,23266150) M cross-section 23266158 11 (DEP,23266155) M+G cross-section 23266158 12 ENDBIB 10 0 23266158 13 COMMON 1 3 23266158 14 EN 23266158 15 EV 23266158 16 0.0253 23266158 17 ENDCOMMON 3 0 23266158 18 DATA 1 1 23266158 19 DATA 23266158 20 NO-DIM 23266158 21 0.028 23266158 22 ENDDATA 3 0 23266158 23 ENDSUBENT 22 0 2326615899999 SUBENT 23266159 20230215 231423266159 1 BIB 9 35 23266159 2 REACTION 1((74-W-186(N,G)74-W-187,,RI,,AV)// 23266159 3 (74-W-186(N,G)74-W-187,,SIG,,AV)) 23266159 4 2((74-W-186(N,G)74-W-187,,RI)// 23266159 5 (74-W-186(N,G)74-W-187,,SIG)) 23266159 6 Q0 value (ratio of resonance integral to thermal 23266159 7 neutron activation cross-section) 23266159 8 SAMPLE - Provider - IRMM 23266159 9 Matrix - Wire,Al alloy 23266159 10 - Elemental content, % weight - 0.01 23266159 11 Average sample thickness, mm - 0.37 23266159 12 - Elemental content, % weight - 0.2 23266159 13 Average sample thickness, mm - 0.5 23266159 14 - Provider - CBNM 23266159 15 Matrix - Foil,Al alloy 23266159 16 Elemental content, % weight - 1. 23266159 17 Average sample thickness, mm - 0.1 23266159 18 (74-W-186,NAT=0.2843) 28.43+-0.19 % 23266159 19 METHOD Measurement at channels S84, Y4, X26 . 23266159 20 DECAY-DATA (74-W-187,23.72HR,DG,134.2,0.1036,DG,479.6,0.2660, 23266159 21 DG,551.5,0.0614,DG,618.3,0.0757,DG,625.5,0.0131, 23266159 22 DG,685.5,0.3320,DG,772.9,0.0502) 23266159 23 23.72+-0.06 hr . 23266159 24 ANALYSIS The Q0 factor was determined by 23266159 25 1- the classical method: through the weighted mean and 23266159 26 observed standard deviation of the 3 irradiation 23266159 27 channels employed (Y4, S84, X26), when inputting Er 23266159 28 factors from the literature. 23266159 29 2- the a-vector method: through the parameters 23266159 30 (m, b) --> determination of the value as well. 23266159 31 ADD-RES Effective resonance Energy was defined by a-vect23266159 32 method to be 22.1 eV ( +-3%, 2sigma). 23266159 33 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266159 34 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266159 35 1(DEP,23266160) Directly measured data . 23266159 36 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266159 37 ENDBIB 35 0 23266159 38 COMMON 2 3 23266159 39 EN-MIN-NM EN-DN 23266159 40 EV EV 23266159 41 0.55 0.0253 23266159 42 ENDCOMMON 3 0 23266159 43 DATA 4 1 23266159 44 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 23266159 45 NO-DIM PER-CENT NO-DIM PER-CENT 23266159 46 13.8 0.5 13.8 2. 23266159 47 ENDDATA 3 0 23266159 48 ENDSUBENT 47 0 2326615999999 SUBENT 23266160 20141210 224123266160 1 BIB 7 38 23266160 2 REACTION ((74-W-186(N,G)74-W-187,,RI)// 23266160 3 (74-W-186(N,G)74-W-187,,SIG)) 23266160 4 Q0 value (ratio of resonance integral to thermal 23266160 5 neutron activation cross-section) 23266160 6 SAMPLE - Provider - IRMM 23266160 7 Matrix - Wire,Al alloy 23266160 8 - Elemental content, % weight - 0.01 23266160 9 Average sample thickness, mm - 0.37 23266160 10 - Elemental content, % weight - 0.2 23266160 11 Average sample thickness, mm - 0.5 23266160 12 - Provider - CBNM 23266160 13 Matrix - Foil,Al alloy 23266160 14 Elemental content, % weight - 1. 23266160 15 Average sample thickness, mm - 0.1 23266160 16 (74-W-186,NAT=0.2843) 28.43+-0.19 % 23266160 17 DECAY-DATA (74-W-187,23.72HR,DG,134.2,0.1036,DG,479.6,0.2660, 23266160 18 DG,551.5,0.0614,DG,618.3,0.0757,DG,625.5,0.0131, 23266160 19 DG,685.5,0.3320,DG,772.9,0.0502) 23266160 20 23.72+-0.06 hr . 23266160 21 FLAG Measurement at channels 23266160 22 (1.) S84, 23266160 23 (2.) Y4, 23266160 24 (3.) X26 23266160 25 ANALYSIS The Q0 factor was determined by the classical method 23266160 26 when inputting effective resonance energy factors 23266160 27 from the literature. 23266160 28 ERR-ANALYS (ERR-SYS) One sigma uncertainty, includes 23266160 29 uncertainties ( 1 sigma) from: 23266160 30 (ERR-1) alpha factor, 23266160 31 (ERR-2) f,Au - ratio of the thermal neutron flux to 23266160 32 epithermal flux for gold, 23266160 33 (ERR-3) effective resonance energy Er, 23266160 34 (ERR-4) Cd transmission factor FCd 23266160 35 (ERR-5) A/ACd -ratio of induced gamma activities, 23266160 36 bare and Cd-covered sample. 23266160 37 (ERR-S) Standard deviation. 23266160 38 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM2-ESM.pdf 23266160 39 (COREL,23266159) Average data . 23266160 40 ENDBIB 38 0 23266160 41 COMMON 2 3 23266160 42 EN-MIN-NM EN-DN 23266160 43 EV EV 23266160 44 0.55 0.0253 23266160 45 ENDCOMMON 3 0 23266160 46 DATA 9 3 23266160 47 DATA ERR-S ERR-1 ERR-2 ERR-3 ERR-4 23266160 48 ERR-5 ERR-SYS FLAG 23266160 49 NO-DIM PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 23266160 50 PER-CENT PER-CENT NO-DIM 23266160 51 13.9 0.85 0.7 1.5 0.0 2.0 23266160 52 1.2 2.85 1. 23266160 53 13.7 0.55 0.15 1.4 0.0 1.5 23266160 54 0.65 2.15 2. 23266160 55 13.8 0.2 0.6 1.35 0.1 1.2 23266160 56 0.6 2.0 3. 23266160 57 ENDDATA 10 0 23266160 58 ENDSUBENT 57 0 2326616099999 SUBENT 23266161 20230215 231423266161 1 BIB 5 11 23266161 2 REACTION (74-W-186(N,G)74-W-187,,SIG,,AV) 23266161 3 SIG-0 - the average thermal neutron cross-section . 23266161 4 for neutrons at an average energy of E0=25.3 meV 23266161 5 or velocity v0=2200 m/s. 23266161 6 ANALYSIS Derived from directly measured data. 23266161 7 ERR-ANALYS (DATA-ERR) One sigma uncertainty. 23266161 8 Uncertainty on exp. SIG-0 value comes from to the 23266161 9 observed SD between gamma-lines. 23266161 10 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266161 11 (DEP,23266162) Directly measured data. 23266161 12 HISTORY (20230215A) SD: SF8=AV added to REACTION codes. 23266161 13 ENDBIB 11 0 23266161 14 COMMON 1 3 23266161 15 EN 23266161 16 EV 23266161 17 0.0253 23266161 18 ENDCOMMON 3 0 23266161 19 DATA 2 1 23266161 20 DATA DATA-ERR 23266161 21 B B 23266161 22 34.9 0.2 23266161 23 ENDDATA 3 0 23266161 24 ENDSUBENT 23 0 2326616199999 SUBENT 23266162 20141210 224123266162 1 BIB 8 40 23266162 2 REACTION (74-W-186(N,G)74-W-187,,SIG) 23266162 3 Directly measured thermal neutron cross-section SIG-0 23266162 4 SAMPLE - Provider - IRMM 23266162 5 Matrix - Wire,Al alloy 23266162 6 - Elemental content, % weight - 0.01 23266162 7 Average sample thickness, mm - 0.37 23266162 8 - Elemental content, % weight - 0.2 23266162 9 Average sample thickness, mm - 0.5 23266162 10 - Provider - CBNM 23266162 11 Matrix - Foil,Al alloy 23266162 12 Elemental content, % weight - 1. 23266162 13 Average sample thickness, mm - 0.1 23266162 14 (74-W-186,NAT=0.2843) 28.43+-0.19 % 23266162 15 DECAY-DATA ((1.)74-W-187,23.72HR,DG,134.2,0.1036) 23266162 16 ((2.)74-W-187,23.72HR,DG,479.6,0.2660) 23266162 17 ((3.)74-W-187,23.72HR,DG,551.5,0.0614) 23266162 18 ((4.)74-W-187,23.72HR,DG,618.3,0.0757) 23266162 19 ((5.)74-W-187,23.72HR,DG,625.5,0.0131) 23266162 20 ((6.)74-W-187,23.72HR,DG,685.5,0.3320) reference line 23266162 21 ((7.)74-W-187,23.72HR,DG,772.9,0.0502) 23266162 22 23.72+-0.06 hr . 23266162 23 METHOD Measurement at channels Y4/Cavity, S84, X26 . 23266162 24 ANALYSIS An thermal neutron cross-section SIG-0 was 23266162 25 extrapolated with aid of the k0-definition, atomic 23266162 26 weight, isotopic composition, the gamma intensities 23266162 27 values. 23266162 28 Defined according to their ADS(activation decay scheme,23266162 29 including decay branching factors). 23266162 30 ADD-RES Measured k0-values with one-sigma uncertainty 23266162 31 E-gamma,keV k0, no-dim.(uncertainty,%) 23266162 32 134.2 1.17E-2 (+-0.2%) 23266162 33 479.6 3.02E-2 (+-0.8%) 23266162 34 551.5 6.92E-3 (+-1.0%) 23266162 35 618.3 8.58E-3 (+-0.9%) 23266162 36 625.5 1.48E-3 (+-1.2%) 23266162 37 685.5 3.71E-2 (+-0.8%) 23266162 38 772.9 5.65E-3 (+-1.6%) 23266162 39 ERR-ANALYS Uncertainty is not given. 23266162 40 STATUS (TABLE) Suppl.material 10967-2012-2132-MOESM3-ESM.pdf 23266162 41 (COREL,23266161) Average data 23266162 42 ENDBIB 40 0 23266162 43 COMMON 1 3 23266162 44 EN 23266162 45 EV 23266162 46 0.0253 23266162 47 ENDCOMMON 3 0 23266162 48 DATA 2 7 23266162 49 DATA DECAY-FLAG 23266162 50 B NO-DIM 23266162 51 34.8 1. 23266162 52 35.1 2. 23266162 53 34.9 3. 23266162 54 35.1 4. 23266162 55 34.8 5. 23266162 56 34.6 6. 23266162 57 34.8 7. 23266162 58 ENDDATA 9 0 23266162 59 ENDSUBENT 58 0 2326616299999 ENDENTRY 162 0 2326699999999