ENTRY 31565 20220825 32083156500000001 SUBENT 31565001 20220825 32083156500100001 BIB 14 53 3156500100002 TITLE Measurement of fission neutron spectrum averaged cross 3156500100003 sections of some threshold reactions on dysprosium: 3156500100004 small scale production of no-carrier-added 153Gd 3156500100005 in a nuclear reactor 3156500100006 AUTHOR (S.Waheed, J.H.Zaidi, S.Ahmad, M.Saleem) 3156500100007 REFERENCE (J,RCA,90,443,2002) 3156500100008 INSTITUTE (3PAKNIL,3PAKQAU) 3156500100009 FACILITY (REAC,3PAKNIL) 10 MW swimming pool type Pakistan 3156500100010 research reactor (PARR-I) at Pinstech. 3156500100011 SAMPLE High purity dysprosium oxide (99.999% pure), weighing 3156500100012 25-50 mg, was filled in a quartz ampoule, sealed and 3156500100013 then placed in an NRX type aluminum irradiation capsule3156500100014 INC-SOURCE (REAC) 3156500100015 DETECTOR (GELI) The radioactivity of the reaction products and 3156500100016 the monitor reactions was determined by gamma-ray 3156500100017 spectrometry using a coaxial 30 cm3 Ge(Li) detector in 3156500100018 conjunction with a 4 K Canberra Series 85 multichannel 3156500100019 analyzer. 3156500100020 INC-SPECT Fast neutron flux density was 7. X 10**13 n/cm2/sec 3156500100021 and the thermal neutron flux density was 3156500100022 2. X 10**14 n/cm2/sec. 3156500100023 Thermal neutron flux density measurement: 3156500100024 197Au(n,g)198Au 98.8 +/- 0.3 b 3156500100025 59Co(n,g)60Co 37.2 +/- 0.2 b 3156500100026 Fast neutron flux density measurement: 3156500100027 54Fe(n,p)54Mn 82.5 +/- 5.0 mb 3156500100028 56Fe(n,p)56Mn 1.07 +/- 0.08 mb 3156500100029 58Ni(n,p)58Co 113. +/- 7.0 mb 3156500100030 60Ni(n,p)60Co 2.3 +/- 0.4 mb 3156500100031 From measurement of the fast/thermal-neutron flux 3156500100032 ratio for monitor reactions having different threshold 3156500100033 it was concluded that the neutron spectrum used was 3156500100034 approximately a fission spectrum. 3156500100035 METHOD (ACTIV,GSPEC) The irradiation time varied from 1 hr to 3156500100036 10 hr depending upon the half-life of the radionuclide.3156500100037 (CHSEP) A new radiochemical separation was proposed. 3156500100038 CORRECTION In converting the count rates to decay rates correc- 3156500100039 tions were applied for radiochemical yields, gamma-ray 3156500100040 intensities, detector efficiencies, counting geometry, 3156500100041 absorption, self-absorption, pile-up effects and 3156500100042 coincidence losses. 3156500100043 ERR-ANALYS (ERR-T) The overall error for each reaction cross 3156500100044 section obtained by summing the individual errors in 3156500100045 quadrature: 3156500100046 (ERR-1) determination of fast neutron flux densities 3156500100047 ~8% 3156500100048 (ERR-2,5.,10.) absolute decay rates 5-10% 3156500100049 (ERR-3,,1.) number of target nuclei <1% 3156500100050 (ERR-4) irradiation and cooling times ~1% 3156500100051 STATUS (TABLE) Table 2 of Radiochim.Acta,90(2002)443 3156500100052 (APRVD) Entry approved by Dr. Jamshed Hussain Zaidi 3156500100053 HISTORY (20051214C) SD 3156500100054 (20220824A) VT. Revision in 002. ERR-ANALYS updated. 3156500100055 ENDBIB 53 0 3156500100056 COMMON 3 3 3156500100057 EN-DUMMY ERR-1 ERR-4 3156500100058 MEV PER-CENT PER-CENT 3156500100059 1.5 8. 1. 3156500100060 ENDCOMMON 3 0 3156500100061 ENDSUBENT 60 0 3156500199999 SUBENT 31565002 20220825 32083156500200001 BIB 3 4 3156500200002 REACTION (66-DY-156(N,P)65-TB-156-M1,,SIG,,FIS) 3156500200003 DECAY-DATA (65-TB-156-M1,5.0HR,DG,88.4,0.0112) 3156500200004 HISTORY (20220825A) VT. REACTION, DECAY-DATA: SF4: M->M1 3156500200005 replaced and DECAY-DATA: DG,226.94,0.6814 deleted. 3156500200006 ENDBIB 4 0 3156500200007 NOCOMMON 0 0 3156500200008 DATA 2 1 3156500200009 DATA ERR-T 3156500200010 MB MB 3156500200011 0.20 0.02 3156500200012 ENDDATA 3 0 3156500200013 ENDSUBENT 12 0 3156500299999 SUBENT 31565003 20051214 31183156500300001 BIB 2 2 3156500300002 REACTION (66-DY-156(N,P)65-TB-156-G,,SIG,,FIS) 3156500300003 DECAY-DATA (65-TB-156-G,5.35D,DG,199.23,0.379,DG,534.35,0.612) 3156500300004 ENDBIB 2 0 3156500300005 NOCOMMON 0 0 3156500300006 DATA 2 1 3156500300007 DATA ERR-T 3156500300008 MB MB 3156500300009 0.26 0.03 3156500300010 ENDDATA 3 0 3156500300011 ENDSUBENT 10 0 3156500399999 SUBENT 31565004 20051214 31183156500400001 BIB 2 2 3156500400002 REACTION (66-DY-156(N,A)64-GD-153,,SIG,,FIS) 3156500400003 DECAY-DATA (64-GD-153,241.6D,DG,97.,0.276,DG,103.,0.196) 3156500400004 ENDBIB 2 0 3156500400005 NOCOMMON 0 0 3156500400006 DATA 2 1 3156500400007 DATA ERR-T 3156500400008 MB MB 3156500400009 0.12 0.016 3156500400010 ENDDATA 3 0 3156500400011 ENDSUBENT 10 0 3156500499999 SUBENT 31565005 20051214 31183156500500001 BIB 2 2 3156500500002 REACTION (66-DY-156(N,2N)66-DY-155,,SIG,,FIS) 3156500500003 DECAY-DATA (66-DY-155,10.0HR,DG,226.94,0.6814) 3156500500004 ENDBIB 2 0 3156500500005 NOCOMMON 0 0 3156500500006 DATA 2 1 3156500500007 DATA ERR-T 3156500500008 MB MB 3156500500009 0.56 0.012 3156500500010 ENDDATA 3 0 3156500500011 ENDSUBENT 10 0 3156500599999 SUBENT 31565006 20051214 31183156500600001 BIB 2 2 3156500600002 REACTION (66-DY-158(N,P)65-TB-158,,SIG,,FIS) 3156500600003 DECAY-DATA (65-TB-158,150.3YR,DG,944.2,0.430,DG,962.17,0.198) 3156500600004 ENDBIB 2 0 3156500600005 NOCOMMON 0 0 3156500600006 DATA 2 1 3156500600007 DATA ERR-T 3156500600008 MB MB 3156500600009 0.28 0.03 3156500600010 ENDDATA 3 0 3156500600011 ENDSUBENT 10 0 3156500699999 SUBENT 31565007 20051214 31183156500700001 BIB 2 2 3156500700002 REACTION (66-DY-160(N,P)65-TB-160,,SIG,,FIS) 3156500700003 DECAY-DATA (65-TB-160,72.3D,DG,298.57,0.268,DG,879.36,0.298) 3156500700004 ENDBIB 2 0 3156500700005 NOCOMMON 0 0 3156500700006 DATA 2 1 3156500700007 DATA ERR-T 3156500700008 MB MB 3156500700009 0.091 0.010 3156500700010 ENDDATA 3 0 3156500700011 ENDSUBENT 10 0 3156500799999 SUBENT 31565008 20051214 31183156500800001 BIB 2 2 3156500800002 REACTION (66-DY-161(N,P)65-TB-161,,SIG,,FIS) 3156500800003 DECAY-DATA (65-TB-161,6.91D,DG,74.59,0.098) 3156500800004 ENDBIB 2 0 3156500800005 NOCOMMON 0 0 3156500800006 DATA 2 1 3156500800007 DATA ERR-T 3156500800008 MB MB 3156500800009 0.031 0.004 3156500800010 ENDDATA 3 0 3156500800011 ENDSUBENT 10 0 3156500899999 SUBENT 31565009 20051214 31183156500900001 BIB 2 2 3156500900002 REACTION (66-DY-162(N,A)64-GD-159,,SIG,,FIS) 3156500900003 DECAY-DATA (64-GD-159,18.56HR,DG,363.5,0.11) 3156500900004 ENDBIB 2 0 3156500900005 NOCOMMON 0 0 3156500900006 DATA 2 1 3156500900007 DATA ERR-T 3156500900008 MB MB 3156500900009 0.0012 0.0002 3156500900010 ENDDATA 3 0 3156500900011 ENDSUBENT 10 0 3156500999999 ENDENTRY 9 0 3156599999999