ENTRY 31583 20060714 31203158300000001 SUBENT 31583001 20060714 31203158300100001 BIB 17 60 3158300100002 TITLE Measurement of fission neutron spectrum averaged cross 3158300100003 sections of some threshold reactions on zirconium: 3158300100004 Production possibility of no-carrier-added 90Y in a 3158300100005 nuclear reactor 3158300100006 AUTHOR (I.A.Abbasi,J.H.Zaidi,M.Arif,S.Waheed,M.S.Subhani) 3158300100007 INSTITUTE (3PAKNIL) 3158300100008 (3PAKPAK) Department of Chemistry, Quaid-e-Azam 3158300100009 University, Islamabad, Pakistan 3158300100010 REFERENCE (J,RCA,94,381,2006) 3158300100011 FACILITY (REAC,3PAKNIL) 10 MW swimming pool type Pakistan 3158300100012 research reactor ( PARR-I) at Pinstech. 3158300100013 SAMPLE High purity zirconyl nitrate (99.999%pure), weighing 3158300100014 25-50 mg, was filled in a quartz ampoule, sealed and 3158300100015 then placed in an NRX type aluminum irradiation 3158300100016 capsule. 3158300100017 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG) 3158300100018 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG) 3158300100019 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG) 3158300100020 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG) 3158300100021 Two of each of the four neutron flux monitor foils (Au,3158300100022 Co, Fe and Ni) were placed in a cylindrical arrangement3158300100023 MONIT-REF (,A.CALAMAND,R,IAEA-156,273,1974) 3158300100024 INC-SPECT From measurement of the fast/thermal -neutron flux 3158300100025 ratio for monitor reactions having different threshold 3158300100026 it was concluded that the neutron spectrum used was 3158300100027 approximately a fission spectrum. 3158300100028 INC-SOURCE (REAC) On the average the fast neutron flux density 3158300100029 was 7x10**13/cm2/s. 3158300100030 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3158300100031 activation of the target nuclei and the radioactive 3158300100032 products were identified by gamma-ray spectrometry. 3158300100033 (CHSEP) 3158300100034 Each cross-section value is a mean of at least six 3158300100035 independent measurements. 3158300100036 DETECTOR (HPGE) The radioactivity of the reaction products and 3158300100037 the monitor reactions was detennined by gamma-ray 3158300100038 spectrometry using a co-axial 270 cm3 HPGe detector in 3158300100039 conjunction with a 4K Canberra Series 85 multichannel 3158300100040 analyzer. 3158300100041 PART-DET (DG) 3158300100042 CORRECTION In converting the count rates to decay rates correc- 3158300100043 tions were applied for radiochemical yields, gamma-ray 3158300100044 intensities, detector efficiencies, counting geometry, 3158300100045 absorption, self-absorption, pile-up effects and 3158300100046 coincidence losses. 3158300100047 ERR-ANALYS (ERR-T) The given uncertainties incorporate both 3158300100048 statistical and systematic uncertainties. 3158300100049 The main sources of uncertainties involved in 3158300100050 cross-section measurements were those associated with 3158300100051 the determination of fast neutron flux densities (<8%) 3158300100052 and absolute decay rates (5 to 10%). 3158300100053 Other sources of uncertainties were small and were due 3158300100054 to uncertainties in the number of target nuclei (< 1%) 3158300100055 as well as in irradiation and cooling times (<<1%). 3158300100056 The overall uncertainty in each reaction cross section 3158300100057 was obtained by summing the individual uncertainties 3158300100058 in quadrature. 3158300100059 STATUS (TABLE) Data taken from Tabl.2 of main reference. 3158300100060 (APRVD) Entry was approved by Dr. J.H.Zaidi 3158300100061 HISTORY (20060821C) SD 3158300100062 ENDBIB 60 0 3158300100063 COMMON 9 6 3158300100064 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3158300100065 MONIT3-ERR MONIT4 MONIT4-ERR 3158300100066 MEV MB MB MB MB MB 3158300100067 MB B B 3158300100068 1.5 82.5 5.0 1.07 .08 113. 3158300100069 7.0 2.3 0.4 3158300100070 ENDCOMMON 6 0 3158300100071 ENDSUBENT 70 0 3158300199999 SUBENT 31583002 20060714 31203158300200001 BIB 2 3 3158300200002 REACTION (40-ZR-90(N,P)39-Y-90-M,,SIG,,FIS) 3158300200003 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.47,0.966, 3158300200004 B-,,0.000021) 3158300200005 ENDBIB 3 0 3158300200006 NOCOMMON 0 0 3158300200007 DATA 2 1 3158300200008 DATA ERR-T 3158300200009 MB MB 3158300200010 0.32 0.06 3158300200011 ENDDATA 3 0 3158300200012 ENDSUBENT 11 0 3158300299999 SUBENT 31583003 20060714 31203158300300001 BIB 2 2 3158300300002 REACTION (40-ZR-90(N,P)39-Y-90-G,,SIG,,FIS) 3158300300003 DECAY-DATA (39-Y-90-G,2.671D,B-,,0.1) 3158300300004 ENDBIB 2 0 3158300300005 NOCOMMON 0 0 3158300300006 DATA 2 1 3158300300007 DATA ERR-T 3158300300008 MB MB 3158300300009 0.76 0.15 3158300300010 ENDDATA 3 0 3158300300011 ENDSUBENT 10 0 3158300399999 SUBENT 31583004 20060714 31203158300400001 BIB 2 2 3158300400002 REACTION (40-ZR-91(N,P)39-Y-91-M,,SIG,,FIS) 3158300400003 DECAY-DATA (39-Y-91-M,49.7MIN,DG,555.56,0.9490) 3158300400004 ENDBIB 2 0 3158300400005 NOCOMMON 0 0 3158300400006 DATA 2 1 3158300400007 DATA ERR-T 3158300400008 MB MB 3158300400009 0.11 0.02 3158300400010 ENDDATA 3 0 3158300400011 ENDSUBENT 10 0 3158300499999 SUBENT 31583005 20060714 31203158300500001 BIB 2 2 3158300500002 REACTION (40-ZR-91(N,P)39-Y-91-G,,SIG,,FIS) 3158300500003 DECAY-DATA (39-Y-91-G,58.51D,B-,,0.1) 3158300500004 ENDBIB 2 0 3158300500005 NOCOMMON 0 0 3158300500006 DATA 2 1 3158300500007 DATA ERR-T 3158300500008 MB MB 3158300500009 0.42 0.08 3158300500010 ENDDATA 3 0 3158300500011 ENDSUBENT 10 0 3158300599999 SUBENT 31583006 20060714 31203158300600001 BIB 2 3 3158300600002 REACTION (40-ZR-92(N,A)38-SR-89,,SIG,,FIS) 3158300600003 DECAY-DATA (38-SR-89,50.55D,DG,909.,0.098, 3158300600004 B-,,0.1) 3158300600005 ENDBIB 3 0 3158300600006 NOCOMMON 0 0 3158300600007 DATA 2 1 3158300600008 DATA ERR-T 3158300600009 MB MB 3158300600010 0.032 0.006 3158300600011 ENDDATA 3 0 3158300600012 ENDSUBENT 11 0 3158300699999 SUBENT 31583007 20060714 31203158300700001 BIB 2 3 3158300700002 REACTION (40-ZR-94(N,A)38-SR-91,,SIG,,FIS) 3158300700003 DECAY-DATA (38-SR-91,9.52HR,DG,1024.,0.33, 3158300700004 B-,,0.1) 3158300700005 ENDBIB 3 0 3158300700006 NOCOMMON 0 0 3158300700007 DATA 2 1 3158300700008 DATA ERR-T 3158300700009 MB MB 3158300700010 0.020 0.004 3158300700011 ENDDATA 3 0 3158300700012 ENDSUBENT 11 0 3158300799999 ENDENTRY 7 0 3158399999999