ENTRY 31563 20220824 32083156300000001 SUBENT 31563001 20220824 32083156300100001 BIB 14 57 3156300100002 TITLE Fission neutron spectrum averaged cross sections of 3156300100003 some threshold reactions on tellurium: estimation 3156300100004 of radioactive impurities in (n,g)-produced 131Te-131I 3156300100005 AUTHOR (M.Arif, J.H.Zaidi, I.H.Qureshi, M.Zafar Iqbal) 3156300100006 REFERENCE (J,RCA,73,45,1996) 3156300100007 INSTITUTE (3PAKNIL) 3156300100008 (3PAKPAK) University of the Punjab, Lahore, Pakistan 3156300100009 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3156300100010 research reactor (PARR-I) at Pinstech. 3156300100011 SAMPLE High purity tellurium oxide granules (99.999% pure), 3156300100012 weighing 25-50 mg, were filled in a quartz ampoule, 3156300100013 sealed and then placed in an NRX type irradiation 3156300100014 capsule. 3156300100015 INC-SOURCE (REAC) 3156300100016 DETECTOR (GELI) The radioactivity of the reaction products and 3156300100017 the monitor reactions was determined by gamma-ray 3156300100018 spectrometry using a coaxial 30 cm3 Ge(Li) detector in 3156300100019 conjunction with a 4 K Canberra Series 85 multichannel 3156300100020 analyzer. 3156300100021 INC-SPECT Fast neutron flux density was 2.25 X 10**13 n/cm2/sec 3156300100022 and the thermal neutron flux density was 3156300100023 6.7 X 10**13 n/cm2/sec. 3156300100024 Thermal neutron flux density measurement: 3156300100025 197Au(n,g)198Au 98.8 +/- 0.3 b 3156300100026 59Co(n,g)60Co 37.2 +/- 0.2 b 3156300100027 Fast neutron flux density measurement: 3156300100028 54Fe(n,p)54Mn 82.5 +/- 5.0 mb 3156300100029 56Fe(n,p)56Mn 1.07 +/- 0.08 mb 3156300100030 58Ni(n,p)58Co 113. +/- 7.0 mb 3156300100031 60Ni(n,p)60Co 2.3 +/- 0.4 mb 3156300100032 From measurement of the fast/thermal-neutron flux 3156300100033 ratio for monitor reactions having different threshold 3156300100034 it was concluded that the neutron spectrum used was 3156300100035 approximately a fission spectrum. 3156300100036 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156300100037 activation of the target nuclei and the radioactive 3156300100038 products were identified by gamma-ray spectrometry. 3156300100039 (CHSEP) A new radiochemical separation was proposed. 3156300100040 Tracer experiments showed the chemical yield of the 3156300100041 procedure up to 98 +/- 2%. 3156300100042 CORRECTION In converting the count rates to decay rates correc- 3156300100043 tions were applied for radiochemical yields, gamma-ray 3156300100044 intensities, detector efficiencies, counting geometry, 3156300100045 absorption, self-absorption, pile-up effects and 3156300100046 coincidence losses. 3156300100047 ERR-ANALYS (ERR-T) The overall error for each reaction cross 3156300100048 section obtained by summing the individual errors in 3156300100049 quadrature: 3156300100050 (ERR-1) determination of fast neutron flux densities 3156300100051 ~5% 3156300100052 (ERR-2,4.,10.) absolute decay rates 4-10% 3156300100053 (ERR-3,,1.) number of target nuclei <1% 3156300100054 (ERR-4) irradiation and cooling times ~1% 3156300100055 STATUS (TABLE) Table 2 of Radiochimica Acta,73(1996)45 3156300100056 (APRVD) Entry approved by Dr. Jamshed Hussain Zaidi 3156300100057 HISTORY (20051214C) SD 3156300100058 (20220824A) VT. Revision in 009-014. ERR-ANALYS updated3156300100059 ENDBIB 57 0 3156300100060 COMMON 3 3 3156300100061 EN-DUMMY ERR-1 ERR-4 3156300100062 MEV PER-CENT PER-CENT 3156300100063 1.5 5. 1. 3156300100064 ENDCOMMON 3 0 3156300100065 ENDSUBENT 64 0 3156300199999 SUBENT 31563002 20051214 31183156300200001 BIB 1 1 3156300200002 REACTION (52-TE-120(N,2N)52-TE-119-M,,SIG,,FIS) 3156300200003 ENDBIB 1 0 3156300200004 NOCOMMON 0 0 3156300200005 DATA 2 1 3156300200006 DATA ERR-T 3156300200007 MICRO-B MICRO-B 3156300200008 181. 15. 3156300200009 ENDDATA 3 0 3156300200010 ENDSUBENT 9 0 3156300299999 SUBENT 31563003 20051214 31183156300300001 BIB 1 1 3156300300002 REACTION (52-TE-120(N,2N)52-TE-119-G,,SIG,,FIS) 3156300300003 ENDBIB 1 0 3156300300004 NOCOMMON 0 0 3156300300005 DATA 2 1 3156300300006 DATA ERR-T 3156300300007 MICRO-B MICRO-B 3156300300008 145. 11. 3156300300009 ENDDATA 3 0 3156300300010 ENDSUBENT 9 0 3156300399999 SUBENT 31563004 20051214 31183156300400001 BIB 1 1 3156300400002 REACTION (52-TE-120(N,P)51-SB-120-M,,SIG,,FIS) 3156300400003 ENDBIB 1 0 3156300400004 NOCOMMON 0 0 3156300400005 DATA 2 1 3156300400006 DATA ERR-T 3156300400007 MICRO-B MICRO-B 3156300400008 521. 47. 3156300400009 ENDDATA 3 0 3156300400010 ENDSUBENT 9 0 3156300499999 SUBENT 31563005 20051214 31183156300500001 BIB 2 2 3156300500002 REACTION (52-TE-120(N,P)51-SB-120-G,,SIG,,FIS) 3156300500003 DECAY-DATA (51-SB-120-G,15.89MIN) 3156300500004 ENDBIB 2 0 3156300500005 NOCOMMON 0 0 3156300500006 DATA 2 1 3156300500007 DATA ERR-T 3156300500008 MICRO-B MICRO-B 3156300500009 394. 40. 3156300500010 ENDDATA 3 0 3156300500011 ENDSUBENT 10 0 3156300599999 SUBENT 31563006 20051214 31183156300600001 BIB 1 1 3156300600002 REACTION (52-TE-122(N,P)51-SB-122,,SIG,,FIS) 3156300600003 ENDBIB 1 0 3156300600004 NOCOMMON 0 0 3156300600005 DATA 2 1 3156300600006 DATA ERR-T 3156300600007 MICRO-B MICRO-B 3156300600008 608. 42. 3156300600009 ENDDATA 3 0 3156300600010 ENDSUBENT 9 0 3156300699999 SUBENT 31563007 20051214 31183156300700001 BIB 1 1 3156300700002 REACTION (52-TE-124(N,P)51-SB-124,,SIG,,FIS) 3156300700003 ENDBIB 1 0 3156300700004 NOCOMMON 0 0 3156300700005 DATA 2 1 3156300700006 DATA ERR-T 3156300700007 MICRO-B MICRO-B 3156300700008 60. 5. 3156300700009 ENDDATA 3 0 3156300700010 ENDSUBENT 9 0 3156300799999 SUBENT 31563008 20051214 31183156300800001 BIB 1 1 3156300800002 REACTION (52-TE-125(N,P)51-SB-125,,SIG,,FIS) 3156300800003 ENDBIB 1 0 3156300800004 NOCOMMON 0 0 3156300800005 DATA 2 1 3156300800006 DATA ERR-T 3156300800007 MICRO-B MICRO-B 3156300800008 167. 12. 3156300800009 ENDDATA 3 0 3156300800010 ENDSUBENT 9 0 3156300899999 SUBENT 31563009 20220824 32083156300900001 BIB 3 4 3156300900002 REACTION (52-TE-126(N,P)51-SB-126-M1+M2,,SIG,,FIS) 3156300900003 DECAY-DATA (51-SB-126-M1,19.03MIN) 3156300900004 HISTORY (20220824A) VT. RAECTION: SF4: M->M1+M2 and DECAY-DATA:3156300900005 M->M1. DATA and ERR-T: MB-> MICRO-B replaced. 3156300900006 ENDBIB 4 0 3156300900007 NOCOMMON 0 0 3156300900008 DATA 2 1 3156300900009 DATA ERR-T 3156300900010 MICRO-B MICRO-B 3156300900011 15. 2. 3156300900012 ENDDATA 3 0 3156300900013 ENDSUBENT 12 0 3156300999999 SUBENT 31563010 20220824 32083156301000001 BIB 2 2 3156301000002 REACTION (52-TE-126(N,P)51-SB-126-G,,SIG,,FIS) 3156301000003 HISTORY (20220824A) VT. DATA and ERR-T: MB-> MICRO-B replaced. 3156301000004 ENDBIB 2 0 3156301000005 NOCOMMON 0 0 3156301000006 DATA 2 1 3156301000007 DATA ERR-T 3156301000008 MICRO-B MICRO-B 3156301000009 31. 2.5 3156301000010 ENDDATA 3 0 3156301000011 ENDSUBENT 10 0 3156301099999 SUBENT 31563011 20220824 32083156301100001 BIB 2 2 3156301100002 REACTION (52-TE-126(N,A)50-SN-123-M,,SIG,,FIS) 3156301100003 HISTORY (20220824A) VT. DATA and ERR-T: MB-> MICRO-B replaced. 3156301100004 ENDBIB 2 0 3156301100005 NOCOMMON 0 0 3156301100006 DATA 2 1 3156301100007 DATA ERR-T 3156301100008 MICRO-B MICRO-B 3156301100009 2. 0.17 3156301100010 ENDDATA 3 0 3156301100011 ENDSUBENT 10 0 3156301199999 SUBENT 31563012 20220824 32083156301200001 BIB 2 2 3156301200002 REACTION (52-TE-126(N,A)50-SN-123-G,,SIG,,FIS) 3156301200003 HISTORY (20220824A) VT. DATA and ERR-T: MB-> MICRO-B replaced. 3156301200004 ENDBIB 2 0 3156301200005 NOCOMMON 0 0 3156301200006 DATA 2 1 3156301200007 DATA ERR-T 3156301200008 MICRO-B MICRO-B 3156301200009 5. 0.4 3156301200010 ENDDATA 3 0 3156301200011 ENDSUBENT 10 0 3156301299999 SUBENT 31563013 20220824 32083156301300001 BIB 3 3 3156301300002 REACTION (52-TE-128(N,A)50-SN-125-M,,SIG,,FIS) 3156301300003 DECAY-DATA (50-SN-125-M,9.52MIN) 3156301300004 HISTORY (20220824A) VT. DATA and ERR-T: MB-> MICRO-B replaced. 3156301300005 ENDBIB 3 0 3156301300006 NOCOMMON 0 0 3156301300007 DATA 2 1 3156301300008 DATA ERR-T 3156301300009 MICRO-B MICRO-B 3156301300010 0.09 0.02 3156301300011 ENDDATA 3 0 3156301300012 ENDSUBENT 11 0 3156301399999 SUBENT 31563014 20220824 32083156301400001 BIB 2 2 3156301400002 REACTION (52-TE-128(N,A)50-SN-125-G,,SIG,,FIS) 3156301400003 HISTORY (20220824A) VT. DATA and ERR-T: MB-> MICRO-B replaced. 3156301400004 ENDBIB 2 0 3156301400005 NOCOMMON 0 0 3156301400006 DATA 2 1 3156301400007 DATA ERR-T 3156301400008 MICRO-B MICRO-B 3156301400009 0.35 0.03 3156301400010 ENDDATA 3 0 3156301400011 ENDSUBENT 10 0 3156301499999 ENDENTRY 14 0 3156399999999