ENTRY 31568 20220126 32073156800000001 SUBENT 31568001 20220126 32073156800100001 BIB 16 44 3156800100002 TITLE Measurement of fission neutron spectrum averaged cross 3156800100003 sections of some threshold reactions on zinc: 3156800100004 small-scale production of no-carrier-added 64Cu in a 3156800100005 nuclear reactor 3156800100006 AUTHOR (I.A.Abbasi, J.H.Zaidi, M.Arif, M.S.Subhani) 3156800100007 INSTITUTE (3PAKQAU,3PAKNIL) 3156800100008 REFERENCE (J,RCA,94,63,2006) 3156800100009 FACILITY (REAC,3PAKNIL) 10 MW swimming pool type Pakistan 3156800100010 research reactor (PARR-I) 3156800100011 SAMPLE High purity zinc oxide (99.999% pure), weighing 3156800100012 25-50 mg, was filled in a quartz ampoule, sealed and 3156800100013 then placed in an NRX type aluminum irradiation 3156800100014 capsule. 3156800100015 DETECTOR (HPGE) 270 cm3, 1.9 keV resolution at 1332.3 keV. 3156800100016 METHOD (ACTIV,GSPEC) The irradiation time varied from 5 min 3156800100017 to 10 hr. 3156800100018 (CHSEP) 3156800100019 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156800100020 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156800100021 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156800100022 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156800100023 MONIT-REF (,A.Calamand,R,IAEA-156,273,1974) 3156800100024 INC-SPECT From measurement of the fast/thermal-neutron flux 3156800100025 ratio for monitor reactions having different threshold 3156800100026 it was concluded that the neutron spectrum used was 3156800100027 approximately a fission spectrum. 3156800100028 INC-SOURCE (REAC) Fast neutron flux density was 3156800100029 7.5 X 10**13 n/cm2/sec and thermal neutron flux density3156800100030 is 2.4 X 10**14 n/cm2/sec. 3156800100031 CORRECTION In converting the count rates to decay rates correc- 3156800100032 tions were applied for radiochemical yields, gamma-ray 3156800100033 intensities, detector efficiencies, counting geometry, 3156800100034 absorption, self-absorption, pile-up effects and 3156800100035 coincidence losses. 3156800100036 ERR-ANALYS (ERR-T) Main sources of errors associated in 3156800100037 cross-section measurements were: 3156800100038 (ERR-1) fast neutron flux densities (8%) 3156800100039 (ERR-2,5.,10.) absolute decay rates (5 to 10% 3156800100040 (ERR-3,,1.) number of target nuclei (<1%) 3156800100041 (ERR-4) irradiation and cooling times (~1%) 3156800100042 STATUS (TABLE) Table 2 of Radiochim. Acta 94 (2006) 63 3156800100043 (APRVD) Entry approved by Dr. Jamshed Hussain Zaidi 3156800100044 HISTORY (20060710C) SD 3156800100045 (20220126U) VT Revision in 002-005 3156800100046 ENDBIB 44 0 3156800100047 COMMON 11 6 3156800100048 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156800100049 MONIT3-ERR MONIT4 MONIT4-ERR ERR-1 ERR-4 3156800100050 MEV MB MB MB MB MB 3156800100051 MB B B PER-CENT PER-CENT 3156800100052 1.5 82.5 5.0 1.07 0.08 113.3156800100053 7.0 2.3 0.4 8. 1. 3156800100054 ENDCOMMON 6 0 3156800100055 ENDSUBENT 54 0 3156800199999 SUBENT 31568002 20220126 32073156800200001 BIB 3 4 3156800200002 REACTION (30-ZN-64(N,P)29-CU-64,,SIG,,FIS) 3156800200003 DECAY-DATA (29-CU-64,12.701HR,DG,1345.78,0.0048, 3156800200004 DG,511.,0.38) 3156800200005 HISTORY (20220126U) VT DECAY-DATA: EC and B- radiation deleted 3156800200006 ENDBIB 4 0 3156800200007 NOCOMMON 0 0 3156800200008 DATA 2 1 3156800200009 DATA ERR-T 3156800200010 MB MB 3156800200011 34.72 6.82 3156800200012 ENDDATA 3 0 3156800200013 ENDSUBENT 12 0 3156800299999 SUBENT 31568003 20220126 32073156800300001 BIB 3 4 3156800300002 REACTION (30-ZN-67(N,P)29-CU-67,,SIG,,FIS) 3156800300003 DECAY-DATA (29-CU-67,2.58D,DG,184.58,0.486, 3156800300004 DG,93.31,0.161) 3156800300005 HISTORY (20220126U) VT DECAY-DATA: B- radiation field deleted 3156800300006 ENDBIB 4 0 3156800300007 NOCOMMON 0 0 3156800300008 DATA 2 1 3156800300009 DATA ERR-T 3156800300010 MB MB 3156800300011 1.37 0.23 3156800300012 ENDDATA 3 0 3156800300013 ENDSUBENT 12 0 3156800399999 SUBENT 31568004 20220126 32073156800400001 BIB 3 4 3156800400002 REACTION (30-ZN-68(N,A)28-NI-65,,SIG,,FIS) 3156800400003 DECAY-DATA (28-NI-65,2.52HR,DG,1481.90,0.235, 3156800400004 DG,1115.58,0.148) 3156800400005 HISTORY (20220126U) VT DECAY-DATA: B- radiation field deleted 3156800400006 ENDBIB 4 0 3156800400007 NOCOMMON 0 0 3156800400008 DATA 2 1 3156800400009 DATA ERR-T 3156800400010 MB MB 3156800400011 0.067 0.012 3156800400012 ENDDATA 3 0 3156800400013 ENDSUBENT 12 0 3156800499999 SUBENT 31568005 20220126 32073156800500001 BIB 3 4 3156800500002 REACTION (30-ZN-64(N,2N)30-ZN-63,,SIG,,FIS) 3156800500003 DECAY-DATA (30-ZN-63,38.1MIN,DG,669.76,0.084, 3156800500004 DG,962.17,0.066) 3156800500005 HISTORY (20220126U) VT DECAY-DATA: EC and B- radiation deleted 3156800500006 ENDBIB 4 0 3156800500007 NOCOMMON 0 0 3156800500008 DATA 2 1 3156800500009 DATA ERR-T 3156800500010 MB MB 3156800500011 0.051 0.009 3156800500012 ENDDATA 3 0 3156800500013 ENDSUBENT 12 0 3156800599999 ENDENTRY 5 0 3156899999999