ENTRY 31560 20130701 31603156000000001 SUBENT 31560001 20130701 31603156000100001 BIB 17 60 3156000100002 TITLE Measurement of fission neutron spectrum averaged cross 3156000100003 sections of some threshold reactions on europium: 3156000100004 small scale production of no-carrier-added 153Sm in 3156000100005 a nuclear reactor 3156000100006 AUTHOR (I.Fatima, J.H.Zaidi, S.Ahmad, M.S.Subhami) 3156000100007 REFERENCE (J,RCA,90,61,2002) 3156000100008 INSTITUTE (3PAKNIL) 3156000100009 (3PAKPAK) Quaid-e-Azam University, Islamabad 3156000100010 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3156000100011 research reactor (PARR-I) at Pinstech. 3156000100012 SAMPLE High purity europium oxide (99.999% pure), weighing 3156000100013 25-50 mg, was filled in a quartz ampoule, sealed and 3156000100014 then placed in an NRX type aluminum irradiation 3156000100015 capsule. 3156000100016 Two of each of the four neutron flux monitor foils 3156000100017 (Au, Co, Fe and Ni), were placed in a cylindrical 3156000100018 arrangement around the ampoule in such a way that the 3156000100019 same neutron flux monitor material was on opposite 3156000100020 sides of the ampoule, allowing thereby a 3156000100021 determination of the effective flux density within 3156000100022 the ampoule. 3156000100023 The foils were washed with acetone; dried and weighed 3156000100024 before attaching to the ampoules. 3156000100025 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156000100026 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156000100027 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156000100028 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156000100029 MONIT-REF (,A.Calamand,R,IAEA-156,273,1974) 3156000100030 INC-SPECT From measurement of the fast/thermal-neutron flux 3156000100031 ratio for monitor reactions having different 3156000100032 threshold it was concluded that the neutron spectrum 3156000100033 used was approximately a fission spectrum. 3156000100034 INC-SOURCE (REAC) 3156000100035 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156000100036 activation of the target nuclei and the radioactive 3156000100037 products were identified by gamma-ray spectrometry. 3156000100038 (CHSEP) A new radiochemical separation was proposed. 3156000100039 Tracer experiments showed the chemical yield of the 3156000100040 procedure up to 98 +/- 2%. 3156000100041 DETECTOR (GELI) The radioactivity of the reaction products and 3156000100042 the monitor reactions was determined by gamma-ray 3156000100043 spectrometry using a coaxial 30 cm3 Ge(Li) detector 3156000100044 in conjunction with a 4 K Canberra Series 85 3156000100045 multichannel analyzer. 3156000100046 PART-DET (DG) 3156000100047 CORRECTION In converting the count rates to decay rates 3156000100048 corrections were applied for radiochemical yields, 3156000100049 gamma-ray intensities, detector efficiencies, 3156000100050 counting geometry, absorption, self-absorption, 3156000100051 pile-up effects and coincidence losses. 3156000100052 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3156000100053 statistical and systematic errors. 3156000100054 (ERR-1) Fast neutron flux densities (8%) 3156000100055 (ERR-2) Radiation and cooling times (1%) 3156000100056 (ERR-3,5.,10.) Absolute decay rates (5-10%) 3156000100057 (ERR-4,,1.) Number of target nuclei (<1%) 3156000100058 STATUS (TABLE) Table 2 of Radiochim.Acta 90(2002)61 3156000100059 (APRVD) Entry approved by Dr. Jamshed Hussain Zaidi 3156000100060 HISTORY (20051214C) SD 3156000100061 (20130701A) On. MONIT4(-ERR): B -> MB, ERR-1, -2 added 3156000100062 ENDBIB 60 0 3156000100063 COMMON 11 6 3156000100064 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156000100065 MONIT3-ERR MONIT4 MONIT4-ERR ERR-1 ERR-2 3156000100066 MEV MB MB MB MB MB 3156000100067 MB MB MB PER-CENT PER-CENT 3156000100068 1.5 82.5 5.0 1.07 0.08 113. 3156000100069 7.0 2.3 0.4 8. 1. 3156000100070 ENDCOMMON 6 0 3156000100071 ENDSUBENT 70 0 3156000199999 SUBENT 31560002 20051214 31183156000200001 BIB 2 2 3156000200002 REACTION (63-EU-153(N,P)62-SM-153,,SIG,,FIS) 3156000200003 DECAY-DATA (62-SM-153,46.75HR,DG,103.2,0.283) 3156000200004 ENDBIB 2 0 3156000200005 NOCOMMON 0 0 3156000200006 DATA 2 1 3156000200007 DATA ERR-T 3156000200008 MB MB 3156000200009 0.20 0.02 3156000200010 ENDDATA 3 0 3156000200011 ENDSUBENT 10 0 3156000299999 SUBENT 31560003 20051214 31183156000300001 BIB 2 2 3156000300002 REACTION (63-EU-153(N,A)61-PM-150,,SIG,,FIS) 3156000300003 DECAY-DATA (61-PM-150,2.68HR,DG,333.9,0.69,DG,1324.4,0.177) 3156000300004 ENDBIB 2 0 3156000300005 NOCOMMON 0 0 3156000300006 DATA 2 1 3156000300007 DATA ERR-T 3156000300008 MB MB 3156000300009 0.131 0.016 3156000300010 ENDDATA 3 0 3156000300011 ENDSUBENT 10 0 3156000399999 SUBENT 31560004 20051214 31183156000400001 BIB 2 2 3156000400002 REACTION (63-EU-151(N,A)61-PM-148-M,,SIG,,FIS) 3156000400003 DECAY-DATA (61-PM-148-M,41.3D,DG,914.8,0.1146,DG,1465.1,0.222) 3156000400004 ENDBIB 2 0 3156000400005 NOCOMMON 0 0 3156000400006 DATA 2 1 3156000400007 DATA ERR-T 3156000400008 MB MB 3156000400009 0.101 0.012 3156000400010 ENDDATA 3 0 3156000400011 ENDSUBENT 10 0 3156000499999 SUBENT 31560005 20051214 31183156000500001 BIB 2 2 3156000500002 REACTION (63-EU-151(N,A)61-PM-148-G,,SIG,,FIS) 3156000500003 DECAY-DATA (61-PM-148-G,5.37D,DG,629.96,0.8862,DG,725.7,0.327) 3156000500004 ENDBIB 2 0 3156000500005 NOCOMMON 0 0 3156000500006 DATA 2 1 3156000500007 DATA ERR-T 3156000500008 MB MB 3156000500009 0.123 0.015 3156000500010 ENDDATA 3 0 3156000500011 ENDSUBENT 10 0 3156000599999 SUBENT 31560006 20051214 31183156000600001 BIB 2 2 3156000600002 REACTION (63-EU-151(N,2N)63-EU-150,,SIG,,FIS) 3156000600003 DECAY-DATA (63-EU-150-M,12.6HR,DG,333.9,0.037,DG,406.5,0.026) 3156000600004 ENDBIB 2 0 3156000600005 NOCOMMON 0 0 3156000600006 DATA 2 1 3156000600007 DATA ERR-T 3156000600008 MB MB 3156000600009 12.1 1.5 3156000600010 ENDDATA 3 0 3156000600011 ENDSUBENT 10 0 3156000699999 ENDENTRY 6 0 3156099999999