ENTRY 31554 20051129 31183155400000001 SUBENT 31554001 20051129 31183155400100001 BIB 17 57 3155400100002 TITLE Fission spectrum averaged cross section measurements 3155400100003 of some neutron threshold reactions of relevance to 3155400100004 medical radionuclide production 3155400100005 AUTHOR (J.H.Zaidi,M.Arif,I.Fatima,S.Waheed, 3155400100006 S.Ahmad,I.H.Qureshi) 3155400100007 REFERENCE (J,RCA,93,547,2005) 3155400100008 INSTITUTE (3PAKNIL) 3155400100009 FACILITY (REAC) 5 MW swimming pool type Pakistan research 3155400100010 reactor ( PARR-I) at Pinstech. 3155400100011 SAMPLE High purity ruthenium sponge, titanium sponge, europium3155400100012 oxide or dysprosium oxide, weighing 25-50 mg each, was 3155400100013 filled in a quartz ampoule, sealed and then placed in 3155400100014 an NRX type alummum irradiation capsule. Two of each 3155400100015 of the three neutron flux monitor foils (Au, Fe and Ni)3155400100016 were placed in a cylindrical arrangement around the 3155400100017 ampoule in such a way that the same neutron flux 3155400100018 monitor material was on opposite sides of the ampoule. 3155400100019 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3155400100020 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3155400100021 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3155400100022 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3155400100023 MONIT-REF (,A.CALAMAND,R,IAEA-156,273,1974) First four monitor 3155400100024 reactions. 3155400100025 INC-SPECT From measurement of the fast/thermal -neutron flux 3155400100026 ratio for monitor reactions having different threshold 3155400100027 it was concluded that the neutron spectrum used was 3155400100028 approximately a fission spectrum. 3155400100029 INC-SOURCE (REAC) 3155400100030 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3155400100031 activation of the target nuclei and the radioactive 3155400100032 products were identified by gamma-ray spectrometry. 3155400100033 (CHSEP) Radiochemical separation of 45Ti, 96gTC, 153Sm,3155400100034 153Gd from the irradiated material. 3155400100035 Each cross section value is a mean of at least four 3155400100036 independent measurements. 3155400100037 DETECTOR (HPGE) The radioactivity of the reaction products and 3155400100038 the monitor reactions was detennined by gamma-ray 3155400100039 spectrometry using a co-axial 245 cm3 HPGe detector in 3155400100040 conjunction with a 4K Canberra Series 85 multichannel 3155400100041 analyzer. 3155400100042 PART-DET (DG) 3155400100043 CORRECTION In converting the count rates to decay rates correc- 3155400100044 tions were applied for radiochemical yields, gamma-ray 3155400100045 intensities, detector efficiencies, counting geometry, 3155400100046 absorption, self-absorption, pile-up effects and 3155400100047 coincidence losses. 3155400100048 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3155400100049 statistical and systematic errors. Main sources of 3155400100050 errors associated in cross-section measurements were 3155400100051 those associated with determination of fast neutron 3155400100052 flux densities (8%) and absolute decay rates (5 to 10%)3155400100053 Other sources of error were small and were due to 3155400100054 uncertainties in the number of target nuclei < 1% and 3155400100055 in radiation and cooling times ( 1%). 3155400100056 STATUS (TABLE) Data taken from Tabl.2 of main reference. 3155400100057 (APRVD) Entry aprroved by Dr. Jamshed Hussain Zaidi 3155400100058 HISTORY (20051129C) SD 3155400100059 ENDBIB 57 0 3155400100060 COMMON 9 6 3155400100061 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3155400100062 MONIT3-ERR MONIT4 MONIT4-ERR 3155400100063 MEV MB MB MB MB MB 3155400100064 MB B B 3155400100065 1.5 82.5 5.0 1.07 .08 113. 3155400100066 7.0 2.3 0.4 3155400100067 ENDCOMMON 6 0 3155400100068 ENDSUBENT 67 0 3155400199999 SUBENT 31554002 20051129 31183155400200001 BIB 3 3 3155400200002 REACTION (22-TI-46(N,2N)22-TI-45,,SIG,,FIS) 3155400200003 DECAY-DATA (22-TI-45,3.08HR,AR,,0.85) 3155400200004 SAMPLE High purity titanium sponge 3155400200005 ENDBIB 3 0 3155400200006 NOCOMMON 0 0 3155400200007 DATA 2 1 3155400200008 DATA ERR-T 3155400200009 MICRO-B MICRO-B 3155400200010 4.57 0.5 3155400200011 ENDDATA 3 0 3155400200012 ENDSUBENT 11 0 3155400299999 SUBENT 31554003 20051129 31183155400300001 BIB 3 5 3155400300002 REACTION (44-RU-96(N,P)43-TC-96,,SIG,,FIS) sum of M+G 3155400300003 DECAY-DATA (43-TC-96-M,51.5MIN) 3155400300004 (43-TC-96-G,4.28D,DG,778.2,0.9976, 3155400300005 DG,1200.5,0.0037) 3155400300006 SAMPLE High purity ruthenium sponge 3155400300007 ENDBIB 5 0 3155400300008 NOCOMMON 0 0 3155400300009 DATA 2 1 3155400300010 DATA ERR-T 3155400300011 MB MB 3155400300012 8.4 1.1 3155400300013 ENDDATA 3 0 3155400300014 ENDSUBENT 13 0 3155400399999 SUBENT 31554004 20051129 31183155400400001 BIB 3 3 3155400400002 REACTION (63-EU-153(N,P)62-SM-153,,SIG,,FIS) 3155400400003 DECAY-DATA (62-SM-153,46.27HR,DG,103.2) 3155400400004 SAMPLE High purity europium oxide 3155400400005 ENDBIB 3 0 3155400400006 NOCOMMON 0 0 3155400400007 DATA 2 1 3155400400008 DATA ERR-T 3155400400009 MB MB 3155400400010 0.20 0.02 3155400400011 ENDDATA 3 0 3155400400012 ENDSUBENT 11 0 3155400499999 SUBENT 31554005 20051129 31183155400500001 BIB 3 3 3155400500002 REACTION (66-DY-156(N,A)64-GD-153,,SIG,,FIS) 3155400500003 DECAY-DATA (64-GD-153,237.9D,DG,103.18) 3155400500004 SAMPLE High purity dysprosium oxide 3155400500005 ENDBIB 3 0 3155400500006 NOCOMMON 0 0 3155400500007 DATA 2 1 3155400500008 DATA ERR-T 3155400500009 MB MB 3155400500010 0.12 0.016 3155400500011 ENDDATA 3 0 3155400500012 ENDSUBENT 11 0 3155400599999 ENDENTRY 5 0 3155499999999