ENTRY 31438 20211005 32023143800000001 SUBENT 31438001 20211005 32023143800100001 BIB 16 58 3143800100002 TITLE Measurement of fission neutron spectrum averaged cross 3143800100003 sections of some threshold reactions on nickel: small 3143800100004 scale production of Co-57 in a nuclear reactor 3143800100005 AUTHOR (J.H.Zaidi,H.M.A.Karim,M.Arif,I.H.Qureshi,S.M.Qaim) 3143800100006 INSTITUTE (3PAKNIL) First four authors 3143800100007 (2GERJUL) last author 3143800100008 REFERENCE (J,RCA,60,169,1993) 3143800100009 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3143800100010 research reactor (PARR-I) at PINSTECH. 3143800100011 SAMPLE (28-NI-58,ENR=0.9966) 3143800100012 Enriched Ni-58 powder (99.66%) or Ni-foil (0.1 mm 3143800100013 thick, 99.99% pure) each weighing 25 to 100 mg, was 3143800100014 sealed in a quartz ampoule, studded with neutron flux 3143800100015 monitor foils and then placed in an nrx type 3143800100016 irradiation capsule. 3143800100017 ASSUMED (ASSUM1,26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3143800100018 (ASSUM2,26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3143800100019 (ASSUM3,13-AL-27(N,A)11-NA-24,,SIG,,FIS) 3143800100020 (ASSUM4,27-CO-59(N,G)27-CO-60,,SIG,,MXW) 3143800100021 (ASSUM5,79-AU-197(N,G)79-AU-198,,SIG,,MXW) 3143800100022 The fast neutron flux densities, effective at the 3143800100023 ampoules, were determined using the first three monitor3143800100024 threshold reactions. The thermal flux density was 3143800100025 determined via the last two reactions. 3143800100026 REL-REF (R,,A.Calamand,R,IAEA-156,273,1974) First three monitor3143800100027 reaction cross sections. 3143800100028 INC-SPECT From measurement of the fast/thermal -neutron flux 3143800100029 ratio for monitor reactions having different threshold 3143800100030 it was concluded that the neutron spectrum used was 3143800100031 approximately a fission spectrum. 3143800100032 INC-SOURCE (REAC) 3143800100033 METHOD (ACTIV,CHSEP) Radiochemical separation of iron, 3143800100034 cobalt and nickel from the irradiated material. 3143800100035 DETECTOR (GELI) 3143800100036 (SILI) For measurement of the low energy gamma-ray 3143800100037 of Co-61. 3143800100038 CORRECTION in converting the count rates to decay rates correc- 3143800100039 tions were applied for radiochemical yields, gamma-ray 3143800100040 intensities, detector efficiencies, counting geometry, 3143800100041 absorption, self-absorption, pile-up effects and 3143800100042 coincidence losses. 3143800100043 ERR-ANALYS (ERR-T) Main sources of errors associated in 3143800100044 cross-section measurements were those associated with: 3143800100045 (ERR-1) determination of fast neutron flux 3143800100046 densities (5%) 3143800100047 (ERR-2,4.,10.) absolute decay rates (4 to 10%). 3143800100048 Other sources of error were small and were due to: 3143800100049 (ERR-3,,1.) uncertainties in the number of 3143800100050 target nuclei < 1% 3143800100051 (ERR-4) in radiation cooling times ( 1%). 3143800100052 The overall error for each cross section was obtained 3143800100053 by summing the individual errors in quadrature. 3143800100054 HISTORY (19940610C) HW 3143800100055 (20100219A) SD:Updated to new date formats,lower case. 3143800100056 (20160624A) VS. SF4, DECAY-DATA corrected in 005. 3143800100057 (20211001A) VS. SF3=X in 003. 3143800100058 STATUS (TABLE) Data are taken from Table 2 of Radiochimica 3143800100059 Acta, vol. 60, no. 4 (1993), pp. 169-172. 3143800100060 ENDBIB 58 0 3143800100061 COMMON 13 9 3143800100062 EN-MEAN ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 3143800100063 ASSUM3-ERR ASSUM4 ASSUM4-ERR ASSUM5 ASSUM5-ERR ERR-1 3143800100064 ERR-4 3143800100065 MEV MB MB MB MB MB 3143800100066 MB B B B B PER-CENT 3143800100067 PER-CENT 3143800100068 1.5 82.5 5.0 1.07 .08 0.72 3143800100069 0.04 37.2 0.2 98.8 0.3 5. 3143800100070 1. 3143800100071 ENDCOMMON 9 0 3143800100072 ENDSUBENT 71 0 3143800199999 SUBENT 31438002 20100220 31443143800200001 BIB 3 4 3143800200002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG,,FIS) 3143800200003 DECAY-DATA (28-NI-57,36.HR,DG,127.3,.129, 3143800200004 DG,1377.6,.779) 3143800200005 COMMENT This subentry supersedes previous subent 30967014. 3143800200006 ENDBIB 4 0 3143800200007 NOCOMMON 0 0 3143800200008 DATA 2 1 3143800200009 DATA ERR-T 3143800200010 MICRO-B MICRO-B 3143800200011 5.1 0.3 3143800200012 ENDDATA 3 0 3143800200013 ENDSUBENT 12 0 3143800299999 SUBENT 31438003 20211005 32023143800300001 BIB 3 8 3143800300002 REACTION (28-NI-58(N,X)27-CO-57,,SIG,,FIS) 3143800300003 DECAY-DATA (27-CO-57,271.8D,DG,14.4,.095, 3143800300004 DG,122.,.856, 3143800300005 DG,136.4,.107) 3143800300006 COMMENT Cross section value for this reaction is the sum of 3143800300007 (n,n'+p), (n,pn) and (n,d) cross sections. 3143800300008 This subentry supersedes previous subent 30967015 3143800300009 (20211001A) VS. SF3=X c.f. Memo CP-D/0999. 3143800300010 ENDBIB 8 0 3143800300011 NOCOMMON 0 0 3143800300012 DATA 2 1 3143800300013 DATA ERR-T 3143800300014 MICRO-B MICRO-B 3143800300015 253. 15. 3143800300016 ENDDATA 3 0 3143800300017 ENDSUBENT 16 0 3143800399999 SUBENT 31438004 20100220 31443143800400001 BIB 2 2 3143800400002 REACTION (28-NI-61(N,P)27-CO-61,,SIG,,FIS) 3143800400003 DECAY-DATA (27-CO-61,1.6HR,DG,67.4,.847) 3143800400004 ENDBIB 2 0 3143800400005 NOCOMMON 0 0 3143800400006 DATA 2 1 3143800400007 DATA ERR-T 3143800400008 MICRO-B MICRO-B 3143800400009 1600. 100. 3143800400010 ENDDATA 3 0 3143800400011 ENDSUBENT 10 0 3143800499999 SUBENT 31438005 20160708 31743143800500001 BIB 3 4 3143800500002 REACTION (28-NI-62(N,P)27-CO-62-M,,SIG,,FIS) 3143800500003 DECAY-DATA (27-CO-62-M,14.MIN,DG,1163.6,.681, 3143800500004 DG,1173.,.979) 3143800500005 HISTORY (20160624A) VS. SF4, DECAY-DATA corrected. 3143800500006 ENDBIB 4 0 3143800500007 NOCOMMON 0 0 3143800500008 DATA 2 1 3143800500009 DATA ERR-T 3143800500010 MICRO-B MICRO-B 3143800500011 9.6 1. 3143800500012 ENDDATA 3 0 3143800500013 ENDSUBENT 12 0 3143800599999 SUBENT 31438006 20100220 31443143800600001 BIB 2 3 3143800600002 REACTION (28-NI-62(N,A)26-FE-59,,SIG,,FIS) 3143800600003 DECAY-DATA (26-FE-59,44.5D,DG,1099.,.565, 3143800600004 DG,1292.,.432) 3143800600005 ENDBIB 3 0 3143800600006 NOCOMMON 0 0 3143800600007 DATA 2 1 3143800600008 DATA ERR-T 3143800600009 MICRO-B MICRO-B 3143800600010 78. 8. 3143800600011 ENDDATA 3 0 3143800600012 ENDSUBENT 11 0 3143800699999 SUBENT 31438007 20100220 31443143800700001 BIB 2 4 3143800700002 REACTION (28-NI-64(N,A)26-FE-61,,SIG,,FIS) 3143800700003 DECAY-DATA (26-FE-61,6.MIN,DG,298.,.222, 3143800700004 DG,1027.,.427, 3143800700005 DG,1205.,.44) 3143800700006 ENDBIB 4 0 3143800700007 NOCOMMON 0 0 3143800700008 DATA 2 1 3143800700009 DATA ERR-T 3143800700010 MICRO-B MICRO-B 3143800700011 66. 8. 3143800700012 ENDDATA 3 0 3143800700013 ENDSUBENT 12 0 3143800799999 ENDENTRY 7 0 3143899999999