ENTRY 21717 20230211 231421717 0 1 SUBENT 21717001 20230211 231421717 1 1 BIB 15 47 21717 1 2 TITLE Reactor neutron activation analysis by a triple 21717 1 3 comparator method 21717 1 4 AUTHOR (F.De Corte, A.Speecke, J.Hoste) 21717 1 5 REFERENCE (J,JRC,3,205,1969) Full Report. 21717 1 6 INSTITUTE (2BLGGHT) Institute for Nuclear Sciences, Ghent Univ. 21717 1 7 FACILITY (REAC,2BLGGHT) THETIS reactor of the Institute for 21717 1 8 Nuclear Sciences at Ghent. 21717 1 9 INC-SOURCE (REAC) Two irradiation positions at a reactor power 21717 1 10 of 15 kW. Thermal and epithermal neutron fluxes at 21717 1 11 both positions was monitored with Co and Au flux 21717 1 12 monitors. 21717 1 13 SAMPLE Samples contained 1 milligram of spectroscopically 21717 1 14 pure In2-O3 mixed with one gram of spec. pure Al2-O3. 21717 1 15 Samples were irradiated with and without a 0.75 mm 21717 1 16 cadmium foil. After dissolution of In2-O3in HCl and 21717 1 17 filtering Al2-O3, gamma counting was started one week 21717 1 18 after irradiation to allow decay of the 54 min In-116 21717 1 19 and 15 hr Na-24 activities, the latter formed by the 21717 1 20 (N,A) reaction on Al-27. 21717 1 21 METHOD (ACTIV) Triple comparator method with analysis of the 21717 1 22 K ratios of the three elements irradiated for 21717 1 23 correction for each thermal to epithermal ratio. 21717 1 24 After irradiation each element was dissolved and 21717 1 25 gamma activity measured in 20 ml glass tubes in a well21717 1 26 type NaI(Tl) scintillation counter. 21717 1 27 DETECTOR (NAICR) Well type NaI(Tl) scintillation counter with 21717 1 28 efficiency determined by the liquid scintillator 21717 1 29 method. 21717 1 30 MONIT-REF (,M.K.Drake+,J,NUC,24,108,1969)-for resonance integrals21717 1 31 D.T.Goldman+,Chart of Nuclides,N.Y.,1966,- for thermal21717 1 32 cross-sections. 21717 1 33 CORRECTION Corrected for half-life, thermal to epithermal flux 21717 1 34 ratio and extraneous activities. 21717 1 35 ERR-ANALYS (ERR-S) Standard deviations from counting statistics, 21717 1 36 not including uncertainties in monitor cross sections 21717 1 37 ADD-RES (COMP) In Table 7 the experimental and calculated 21717 1 38 K-factors (K=S1/S2 ,where A1 and A2 are the specific 21717 1 39 photopeak activities of the isotope investigated and 21717 1 40 comparator, respectively) for isotopes of Na-24,Sc-46,21717 1 41 Cu-64,Ga-72, As-76, Sb-122 and comparators of Co-60, 21717 1 42 In-114m, Au-198 are compared. 21717 1 43 STATUS (TABLE) Table 4, J.Radioan.Chem.,3,205,1969. 21717 1 44 HISTORY (19810108C) 21717 1 45 (20080306U) M.M. BIB information was added. Dates were 21717 1 46 corrected for 4-digits year. Free text was corrected 21717 1 47 for "human-readable". 21717 1 48 (20230211A) SD: Corrections in Subents 002, 003. 21717 1 49 ENDBIB 47 0 21717 1 50 NOCOMMON 0 0 21717 1 51 ENDSUBENT 50 0 21717 199999 SUBENT 21717002 20230211 231421717 2 1 BIB 6 25 21717 2 2 REACTION (49-IN-113(N,G)49-IN-114-M,,SIG,,MXW) 21717 2 3 INC-SPECT Thermal Maxwellian reactor spectrum. 21717 2 4 Average ratios of thermal to epithermal fluxes are 21717 2 5 23.7 at 1st position, 119. at 2nd position. 21717 2 6 ANALYSIS Average of six measurements at two irradiation 21717 2 7 positions. 21717 2 8 DECAY-DATA (49-IN-114-M,50.0D,DG,192.) An internal 21717 2 9 conversion ratio of 5. was assumed for the 192keV 21717 2 10 gamma. 21717 2 11 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG,,MXW) 21717 2 12 Value taken as 37.0 b. 21717 2 13 ((MONIT2)27-CO-59(N,G)27-CO-60,,RI) 21717 2 14 The resonance integral was taken as 75.0 b. 21717 2 15 ((MONIT3)79-AU-197(N,G)79-AU-198,,SIG) 21717 2 16 ((MONIT4)79-AU-197(N,G)79-AU-198,,RI) 21717 2 17 Gold was used as a second monitor with values of 98.8b21717 2 18 and 1550.b for the thermal cross section and the 21717 2 19 resonance integral. 21717 2 20 HISTORY (19810108C) 21717 2 21 (20080306A) M.M. Obsolete code in REACTION "SIG/SUM" 21717 2 22 was changed into "SIG". Obsolete codes in MONIT1 line 21717 2 23 were changed "27-CO-60-G+M,,SIG/SUM," into 21717 2 24 "27-CO-60,,SIG," . 21717 2 25 (20230211A) SD: SF4=In-114-M1+M2 -> In-114m in REACTION21717 2 26 code. 21717 2 27 ENDBIB 25 0 21717 2 28 NOCOMMON 0 0 21717 2 29 DATA 7 1 21717 2 30 EN-DUMMY MONIT1 DATA ERR-S MONIT2 MONIT3 21717 2 31 MONIT4 21717 2 32 EV B B B B B 21717 2 33 B 21717 2 34 0.0253 37. 9.45 0.38 75.0 98.821717 2 35 1550. 21717 2 36 ENDDATA 6 0 21717 2 37 ENDSUBENT 36 0 21717 299999 SUBENT 21717003 20230211 231421717 3 1 BIB 5 21 21717 3 2 REACTION (49-IN-113(N,G)49-IN-114-M,,RI) 21717 3 3 ANALYSIS Average of six measurements at two irradiation 21717 3 4 positions. 21717 3 5 DECAY-DATA (49-IN-114-M,49.0D,DG,192.) The internal 21717 3 6 conversion ratio was taken as 5 for the 192keV gamma. 21717 3 7 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,RI) Value taken 21717 3 8 as 75. b. The thermal cross section was taken 21717 3 9 as 37.0 b. 21717 3 10 ((MONIT2)27-CO-59(N,G)27-CO-60,,SIG) 21717 3 11 ((MONIT3)79-AU-197(N,G)79-AU-198,,SIG) 21717 3 12 ((MONIT4)79-AU-197(N,G)79-AU-198,,RI) 21717 3 13 Gold was used as a second monitor with values of 98.8 21717 3 14 and 1550 b taken for the thermal cross section and 21717 3 15 resonance integral. 21717 3 16 HISTORY (19810108C) 21717 3 17 (20080306A) M.M. Obsolete code in REACTION line was 21717 3 18 changed: ",RI/SUM)" into ",RI)". Obsolete codes in 21717 3 19 MONIT1 line were changed "27-CO-60-G+M,,RI/SUM)" into 21717 3 20 "27-CO-60,,RI)". 21717 3 21 (20230211A) SD: SF4=In-114-M1+M2 -> In-114m in REACTION21717 3 22 code. 21717 3 23 ENDBIB 21 0 21717 3 24 NOCOMMON 0 0 21717 3 25 DATA 7 1 21717 3 26 EN-MIN MONIT1 DATA ERR-S MONIT2 MONIT3 21717 3 27 MONIT4 21717 3 28 EV B B B B B 21717 3 29 B 21717 3 30 0.5 75. 258. 18. 37.0 98.821717 3 31 1550. 21717 3 32 ENDDATA 6 0 21717 3 33 ENDSUBENT 32 0 21717 399999 ENDENTRY 3 0 2171799999999