ENTRY 31566 20060124 31183156600000001 SUBENT 31566001 20060124 31183156600100001 BIB 17 58 3156600100002 TITLE Fission neutron spectrum averaged cross sections of 3156600100003 some threshold reactions on cadmium: production 3156600100004 feasibility of no-carrier-added 103Pd in a nuclear 3156600100005 reactor 3156600100006 AUTHOR (I.A.Abbasi,J.H.Zaidi,M.Arif,M.S.Subhani) 3156600100007 REFERENCE (J,RCA,94,1,2006) 3156600100008 INSTITUTE (3PAKNIL) 3156600100009 (3PAKPAK) Quaid-e-Azam University, Islamabad 3156600100010 FACILITY (REAC,3PAKNIL) 10 MW swimming pool type Pakistan 3156600100011 research reactor ( PARR-I) at Pinstech. 3156600100012 SAMPLE High purity cadmium oxide (99.999% pure), weighing 3156600100013 25-50 mg, was placed in a quartz ampoule, sealed and 3156600100014 then placed in an NRX type aluminum irradiation capsule3156600100015 Two of each of the threer neutron flux monitor foils 3156600100016 (Au, Fe, and Ni),were placed in a cylindrical 3156600100017 arrangement around the ampoule in such a way that the 3156600100018 same neutron flux monitor material was on opposite 3156600100019 sides of the ampoule, allowing thereby a determination 3156600100020 of the effective flux density within the ampoule. 3156600100021 The foils were washed with acetone; dried and weighed 3156600100022 before attaching to the ampoules. 3156600100023 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156600100024 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156600100025 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156600100026 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156600100027 MONIT-REF (,A.CALAMAND,R,IAEA-156,273,1974) First four monitor 3156600100028 reactions. 3156600100029 INC-SPECT From measurement of the fast/thermal -neutron flux 3156600100030 ratio for monitor reactions having different threshold 3156600100031 it was concluded that the neutron spectrum used was 3156600100032 approximately a fission spectrum. 3156600100033 INC-SOURCE (REAC) 3156600100034 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156600100035 activation of the target nuclei and the radioactive 3156600100036 products were identified by gamma-ray spectrometry. 3156600100037 (CHSEP) A new radiochemical separation was proposed. 3156600100038 DETECTOR (HPGE) The radioactivity of the reaction products and 3156600100039 the monitor reactions was determined by gamma-ray 3156600100040 spectrometry using a coaxial 270 cm3 HPGe detector in 3156600100041 conjunction with a 4 K Canberra Series 85 multichannel 3156600100042 analyzer. 3156600100043 PART-DET (DG) 3156600100044 CORRECTION In converting the count rates to decay rates correc- 3156600100045 tions were applied for radiochemical yields, gamma-ray 3156600100046 intensities, detector efficiencies, counting geometry, 3156600100047 absorption, self-absorption, pile-up effects and 3156600100048 coincidence losses. 3156600100049 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3156600100050 statistical and systematic errors. Main sources of 3156600100051 errors associated in cross-section measurements were 3156600100052 those associated with determination of fast neutron 3156600100053 flux densities (8%) and absolute decay rates (5 to 10%)3156600100054 Other sources of error were small and were due to 3156600100055 uncertainties in the number of target nuclei < 1% and 3156600100056 in radiation and cooling times ( 1%). 3156600100057 STATUS (TABLE) Data taken from Tabl.2 of main reference. 3156600100058 (APRVD) Entry aprroved by Dr. Jamshed Hussain Zaidi 3156600100059 HISTORY (20060124C) SD 3156600100060 ENDBIB 58 0 3156600100061 COMMON 9 6 3156600100062 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156600100063 MONIT3-ERR MONIT4 MONIT4-ERR 3156600100064 MEV MB MB MB MB MB 3156600100065 MB B B 3156600100066 1.5 82.5 5.0 1.07 .08 113. 3156600100067 7.0 2.3 0.4 3156600100068 ENDCOMMON 6 0 3156600100069 ENDSUBENT 68 0 3156600199999 SUBENT 31566002 20060124 31183156600200001 BIB 1 1 3156600200002 REACTION (48-CD-106(N,A)46-PD-103,,SIG,,FIS) 3156600200003 ENDBIB 1 0 3156600200004 NOCOMMON 0 0 3156600200005 DATA 2 1 3156600200006 DATA ERR-T 3156600200007 MB MB 3156600200008 2.29 0.69 3156600200009 ENDDATA 3 0 3156600200010 ENDSUBENT 9 0 3156600299999 SUBENT 31566003 20060124 31183156600300001 BIB 2 2 3156600300002 REACTION (48-CD-106(N,P)47-AG-106-M,,SIG,,FIS) 3156600300003 DECAY-DATA (47-AG-106-M,8.3D) 3156600300004 ENDBIB 2 0 3156600300005 NOCOMMON 0 0 3156600300006 DATA 2 1 3156600300007 DATA ERR-T 3156600300008 MB MB 3156600300009 5.55 0.76 3156600300010 ENDDATA 3 0 3156600300011 ENDSUBENT 10 0 3156600399999 SUBENT 31566004 20060124 31183156600400001 BIB 1 1 3156600400002 REACTION (48-CD-108(N,P)47-AG-108-M,,SIG,,FIS) 3156600400003 ENDBIB 1 0 3156600400004 NOCOMMON 0 0 3156600400005 DATA 2 1 3156600400006 DATA ERR-T 3156600400007 MB MB 3156600400008 0.65 0.09 3156600400009 ENDDATA 3 0 3156600400010 ENDSUBENT 9 0 3156600499999 SUBENT 31566005 20060124 31183156600500001 BIB 1 1 3156600500002 REACTION (48-CD-110(N,P)47-AG-110-M,,SIG,,FIS) 3156600500003 ENDBIB 1 0 3156600500004 NOCOMMON 0 0 3156600500005 DATA 2 1 3156600500006 DATA ERR-T 3156600500007 MB MB 3156600500008 0.18 0.03 3156600500009 ENDDATA 3 0 3156600500010 ENDSUBENT 9 0 3156600599999 SUBENT 31566006 20060124 31183156600600001 BIB 1 1 3156600600002 REACTION (48-CD-111(N,P)47-AG-111,,SIG,,FIS) 3156600600003 ENDBIB 1 0 3156600600004 NOCOMMON 0 0 3156600600005 DATA 2 1 3156600600006 DATA ERR-T 3156600600007 MB MB 3156600600008 2.02 0.29 3156600600009 ENDDATA 3 0 3156600600010 ENDSUBENT 9 0 3156600699999 SUBENT 31566007 20060124 31183156600700001 BIB 2 2 3156600700002 REACTION (48-CD-112(N,A)46-PD-109,,SIG,,FIS) 3156600700003 DECAY-DATA (46-PD-109,13.7HR) 3156600700004 ENDBIB 2 0 3156600700005 NOCOMMON 0 0 3156600700006 DATA 2 1 3156600700007 DATA ERR-T 3156600700008 MB MB 3156600700009 0.73 0.11 3156600700010 ENDDATA 3 0 3156600700011 ENDSUBENT 10 0 3156600799999 SUBENT 31566008 20060124 31183156600800001 BIB 1 1 3156600800002 REACTION (48-CD-112(N,P)47-AG-112,,SIG,,FIS) 3156600800003 ENDBIB 1 0 3156600800004 NOCOMMON 0 0 3156600800005 DATA 2 1 3156600800006 DATA ERR-T 3156600800007 MICRO-B MICRO-B 3156600800008 15.7 2.3 3156600800009 ENDDATA 3 0 3156600800010 ENDSUBENT 9 0 3156600899999 SUBENT 31566009 20060124 31183156600900001 BIB 1 1 3156600900002 REACTION (48-CD-113(N,P)47-AG-113,,SIG,,FIS) 3156600900003 ENDBIB 1 0 3156600900004 NOCOMMON 0 0 3156600900005 DATA 2 1 3156600900006 DATA ERR-T 3156600900007 MB MB 3156600900008 0.102 0.015 3156600900009 ENDDATA 3 0 3156600900010 ENDSUBENT 9 0 3156600999999 SUBENT 31566010 20060124 31183156601000001 BIB 2 2 3156601000002 REACTION (48-CD-114(N,A)46-PD-111,,SIG,,FIS) 3156601000003 DECAY-DATA (46-PD-111-M,5.5HR) 3156601000004 ENDBIB 2 0 3156601000005 NOCOMMON 0 0 3156601000006 DATA 2 1 3156601000007 DATA ERR-T 3156601000008 MICRO-B MICRO-B 3156601000009 0.17 0.02 3156601000010 ENDDATA 3 0 3156601000011 ENDSUBENT 10 0 3156601099999 ENDENTRY 10 0 3156699999999