ENTRY 14111 20061003 13421411100000001 SUBENT 14111001 20061003 13421411100100001 BIB 11 30 1411100100002 INSTITUTE (1CANMPT) 1411100100003 REFERENCE (J,NIM/A,564,669,2006) 1411100100004 AUTHOR (J.St-Pierre,G.Kennedy) 1411100100005 TITLE Re-measurement of Q0 and k0 values for 14 nuclides 1411100100006 FACILITY (REAC,1CANMPT) All irradiations were carried out in 1411100100007 the inner and outer irradiation sites of the 1411100100008 Ecole Polytechnique SLOWPOKE reactor. 1411100100009 INC-SOURCE (REAC) The shape parameter, alpha, of the epithermal 1411100100010 neutron spectrum of the inner irradiation site was 1411100100011 measured by the Cd-ratio for multi-monitor method 1411100100012 using six reactions with well-known Q0 values 1411100100013 METHOD (ACTIV) 1411100100014 DETECTOR (HPGE) germanium detector 1411100100015 SAMPLE Aliquots of the 13 elements studied and the Au 1411100100016 comparator, with volume 1mL and approximate mass 1411100100017 100 microg, were prepared with an estimated accuracy 1411100100018 of 1%. Specpure Plasma Standards, 1000 ppm solutions 1411100100019 certified to be accurate to 0.3%, were purchased from 1411100100020 Alfa Aesar, USA for Ag, As, Au, Cd, Cs, In, Pd, Re, 1411100100021 Rb, Sr, Ta and Tm. 1411100100022 CORRECTION For all the 100 microg standards on filter paper, with 1411100100023 approximate volume 1 mL, the effects of both thermal 1411100100024 and epithermal neutron self-shielding were negligible.1411100100025 For thermal neutron self-shielding, the worst case 1411100100026 was Cd, for which it was estimated to be 0.1% 1411100100027 (Gth = 0.999). For epithermal neutron self-shielding, 1411100100028 the worst cases were As, for which it was estimated 1411100100029 to be 0.08%, and I, for which it was estimated to 1411100100030 be 0.06%. 1411100100031 HISTORY (20061003C) DR 1411100100032 ENDBIB 30 0 1411100100033 COMMON 2 3 1411100100034 EN-MIN-NM EN-MEAN-DN 1411100100035 EV EV 1411100100036 0.55 0.0253 1411100100037 ENDCOMMON 3 0 1411100100038 ENDSUBENT 37 0 1411100199999 SUBENT 14111002 20061003 13421411100200001 BIB 3 6 1411100200002 REACTION ((33-AS-75(N,G)33-AS-76,,RI)// 1411100200003 (33-AS-75(N,G)33-AS-76,,SIG)) 1411100200004 Q0 value (ratio of resonance integral to thermal 1411100200005 neutron activation cross-section) 1411100200006 ERR-ANALYS (ERR-T) Total uncertainty 1411100200007 STATUS (TABLE) Data taken from table 1. 1411100200008 ENDBIB 6 0 1411100200009 NOCOMMON 0 0 1411100200010 DATA 2 1 1411100200011 DATA ERR-T 1411100200012 NO-DIM NO-DIM 1411100200013 15.0 0.4 1411100200014 ENDDATA 3 0 1411100200015 ENDSUBENT 14 0 1411100299999 SUBENT 14111003 20061003 13421411100300001 BIB 3 6 1411100300002 REACTION ((37-RB-87(N,G)37-RB-88,,RI)// 1411100300003 (37-RB-87(N,G)37-RB-88,,SIG)) 1411100300004 Q0 value (ratio of resonance integral to thermal 1411100300005 neutron activation cross-section) 1411100300006 ERR-ANALYS (ERR-T) Total uncertainty 1411100300007 STATUS (TABLE) Data taken from table 1. 1411100300008 ENDBIB 6 0 1411100300009 NOCOMMON 0 0 1411100300010 DATA 2 1 1411100300011 DATA ERR-T 1411100300012 NO-DIM NO-DIM 1411100300013 23.5 0.5 1411100300014 ENDDATA 3 0 1411100300015 ENDSUBENT 14 0 1411100399999 SUBENT 14111004 20061003 13421411100400001 BIB 3 6 1411100400002 REACTION ((38-SR-87(N,G)38-SR-88,,RI)// 1411100400003 (38-SR-87(N,G)38-SR-88,,SIG)) 1411100400004 Q0 value (ratio of resonance integral to thermal 1411100400005 neutron activation cross-section) 1411100400006 ERR-ANALYS (ERR-T) Total uncertainty 1411100400007 STATUS (TABLE) Data taken from table 1. 1411100400008 ENDBIB 6 0 1411100400009 NOCOMMON 0 0 1411100400010 DATA 2 1 1411100400011 DATA ERR-T 1411100400012 NO-DIM NO-DIM 1411100400013 13.3 0.3 1411100400014 ENDDATA 3 0 1411100400015 ENDSUBENT 14 0 1411100499999 SUBENT 14111005 20061003 13421411100500001 BIB 3 6 1411100500002 REACTION ((46-PD-108(N,G)46-PD-109,,RI)// 1411100500003 (46-PD-108(N,G)46-PD-109,,SIG)) 1411100500004 Q0 value (ratio of resonance integral to thermal 1411100500005 neutron activation cross-section) 1411100500006 ERR-ANALYS (ERR-T) Total uncertainty 1411100500007 STATUS (TABLE) Data taken from table 1. 1411100500008 ENDBIB 6 0 1411100500009 NOCOMMON 0 0 1411100500010 DATA 2 1 1411100500011 DATA ERR-T 1411100500012 NO-DIM NO-DIM 1411100500013 26.3 0.4 1411100500014 ENDDATA 3 0 1411100500015 ENDSUBENT 14 0 1411100599999 SUBENT 14111006 20061003 13421411100600001 BIB 3 6 1411100600002 REACTION ((47-AG-109(N,G)47-AG-110-M,,RI)// 1411100600003 (47-AG-109(N,G)47-AG-110-M,,SIG)) 1411100600004 Q0 value (ratio of resonance integral to thermal 1411100600005 neutron activation cross-section) 1411100600006 ERR-ANALYS (ERR-T) Total uncertainty 1411100600007 STATUS (TABLE) Data taken from table 1. 1411100600008 ENDBIB 6 0 1411100600009 NOCOMMON 0 0 1411100600010 DATA 2 1 1411100600011 DATA ERR-T 1411100600012 NO-DIM NO-DIM 1411100600013 16.3 0.4 1411100600014 ENDDATA 3 0 1411100600015 ENDSUBENT 14 0 1411100699999 SUBENT 14111007 20061003 13421411100700001 BIB 3 6 1411100700002 REACTION ((48-CD-114(N,G)48-CD-115,,RI)// 1411100700003 (48-CD-114(N,G)48-CD-115,,SIG)) 1411100700004 Q0 value (ratio of resonance integral to thermal 1411100700005 neutron activation cross-section) 1411100700006 ERR-ANALYS (ERR-T) Total uncertainty 1411100700007 STATUS (TABLE) Data taken from table 1. 1411100700008 ENDBIB 6 0 1411100700009 NOCOMMON 0 0 1411100700010 DATA 2 1 1411100700011 DATA ERR-T 1411100700012 NO-DIM NO-DIM 1411100700013 39.6 0.5 1411100700014 ENDDATA 3 0 1411100700015 ENDSUBENT 14 0 1411100799999 SUBENT 14111008 20061003 13421411100800001 BIB 3 6 1411100800002 REACTION ((49-IN-115(N,G)49-IN-116-M,,RI)// 1411100800003 (49-IN-115(N,G)49-IN-116-M,,SIG)) 1411100800004 Q0 value (ratio of resonance integral to thermal 1411100800005 neutron activation cross-section) 1411100800006 ERR-ANALYS (ERR-T) Total uncertainty 1411100800007 STATUS (TABLE) Data taken from table 1. 1411100800008 ENDBIB 6 0 1411100800009 NOCOMMON 0 0 1411100800010 DATA 2 1 1411100800011 DATA ERR-T 1411100800012 NO-DIM NO-DIM 1411100800013 16.8 0.3 1411100800014 ENDDATA 3 0 1411100800015 ENDSUBENT 14 0 1411100899999 SUBENT 14111009 20061003 13421411100900001 BIB 3 6 1411100900002 REACTION ((53-I-127(N,G)53-I-128,,RI)// 1411100900003 (53-I-127(N,G)53-I-128,,SIG)) 1411100900004 Q0 value (ratio of resonance integral to thermal 1411100900005 neutron activation cross-section) 1411100900006 ERR-ANALYS (ERR-T) Total uncertainty 1411100900007 STATUS (TABLE) Data taken from table 1. 1411100900008 ENDBIB 6 0 1411100900009 NOCOMMON 0 0 1411100900010 DATA 2 1 1411100900011 DATA ERR-T 1411100900012 NO-DIM NO-DIM 1411100900013 24.4 0.5 1411100900014 ENDDATA 3 0 1411100900015 ENDSUBENT 14 0 1411100999999 SUBENT 14111010 20061003 13421411101000001 BIB 3 6 1411101000002 REACTION ((55-CS-133(N,G)55-CS-134-M,,RI)// 1411101000003 (55-CS-133(N,G)55-CS-134-M,,SIG)) 1411101000004 Q0 value (ratio of resonance integral to thermal 1411101000005 neutron activation cross-section) 1411101000006 ERR-ANALYS (ERR-T) Total uncertainty 1411101000007 STATUS (TABLE) Data taken from table 1. 1411101000008 ENDBIB 6 0 1411101000009 NOCOMMON 0 0 1411101000010 DATA 2 1 1411101000011 DATA ERR-T 1411101000012 NO-DIM NO-DIM 1411101000013 12.3 0.2 1411101000014 ENDDATA 3 0 1411101000015 ENDSUBENT 14 0 1411101099999 SUBENT 14111011 20061003 13421411101100001 BIB 3 6 1411101100002 REACTION ((55-CS-133(N,G)55-CS-134,,RI)// 1411101100003 (55-CS-133(N,G)55-CS-134,,SIG)) 1411101100004 Q0 value (ratio of resonance integral to thermal 1411101100005 neutron activation cross-section) 1411101100006 ERR-ANALYS (ERR-T) Total uncertainty 1411101100007 STATUS (TABLE) Data taken from table 1. 1411101100008 ENDBIB 6 0 1411101100009 NOCOMMON 0 0 1411101100010 DATA 2 1 1411101100011 DATA ERR-T 1411101100012 NO-DIM NO-DIM 1411101100013 15.1 0.3 1411101100014 ENDDATA 3 0 1411101100015 ENDSUBENT 14 0 1411101199999 SUBENT 14111012 20061003 13421411101200001 BIB 3 6 1411101200002 REACTION ((56-BA-130(N,G)56-BA-131,,RI)// 1411101200003 (56-BA-130(N,G)56-BA-131,,SIG)) 1411101200004 Q0 value (ratio of resonance integral to thermal 1411101200005 neutron activation cross-section) 1411101200006 ERR-ANALYS (ERR-T) Total uncertainty 1411101200007 STATUS (TABLE) Data taken from table 1. 1411101200008 ENDBIB 6 0 1411101200009 NOCOMMON 0 0 1411101200010 DATA 2 1 1411101200011 DATA ERR-T 1411101200012 NO-DIM NO-DIM 1411101200013 21.6 0.5 1411101200014 ENDDATA 3 0 1411101200015 ENDSUBENT 14 0 1411101299999 SUBENT 14111013 20061003 13421411101300001 BIB 3 6 1411101300002 REACTION ((69-TM-169(N,G)69-TM-170,,RI)// 1411101300003 (69-TM-169(N,G)69-TM-170,,SIG)) 1411101300004 Q0 value (ratio of resonance integral to thermal 1411101300005 neutron activation cross-section) 1411101300006 ERR-ANALYS (ERR-T) Total uncertainty 1411101300007 STATUS (TABLE) Data taken from table 1. 1411101300008 ENDBIB 6 0 1411101300009 NOCOMMON 0 0 1411101300010 DATA 2 1 1411101300011 DATA ERR-T 1411101300012 NO-DIM NO-DIM 1411101300013 14.3 0.3 1411101300014 ENDDATA 3 0 1411101300015 ENDSUBENT 14 0 1411101399999 SUBENT 14111014 20061003 13421411101400001 BIB 3 6 1411101400002 REACTION ((73-TA-181(N,G)73-TA-182,,RI)// 1411101400003 (73-TA-181(N,G)73-TA-182,,SIG)) 1411101400004 Q0 value (ratio of resonance integral to thermal 1411101400005 neutron activation cross-section) 1411101400006 ERR-ANALYS (ERR-T) Total uncertainty 1411101400007 STATUS (TABLE) Data taken from table 1. 1411101400008 ENDBIB 6 0 1411101400009 NOCOMMON 0 0 1411101400010 DATA 2 1 1411101400011 DATA ERR-T 1411101400012 NO-DIM NO-DIM 1411101400013 36.9 1.4 1411101400014 ENDDATA 3 0 1411101400015 ENDSUBENT 14 0 1411101499999 ENDENTRY 14 0 1411199999999