ENTRY 31562 20080909 31313156200000001 SUBENT 31562001 20080909 31313156200100001 BIB 17 52 3156200100002 TITLE Fission neutron spectrum averaged cross sections of 3156200100003 some threshold reactions on Tin: small scale 3156200100004 production of 111In in a nuclear reactor 3156200100005 AUTHOR (M.Arif,J.H.Zaidi,I.H.Qureshi,M.Zafar Iqbal) 3156200100006 REFERENCE (J,RCA,75,175,1996) 3156200100007 INSTITUTE (3PAKNIL) 3156200100008 (3PAKPAK) University of the Punjab, Lahore, Pakistan 3156200100009 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3156200100010 SAMPLE Tin-foil (0.1 mm thick, 99.999% pure) weighing 50 mg, 3156200100011 was sealed in a quartz ampoule, studded with neutron 3156200100012 flux monitor foils and then placed in an NRX type 3156200100013 irradiation capsule. The monitor foils were washed 3156200100014 with acetone; dried and weighed before attaching to 3156200100015 the ampoules. 3156200100016 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156200100017 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156200100018 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156200100019 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156200100020 MONIT-REF (,A.CALAMAND,R,IAEA-156,273,1974) First four monitor 3156200100021 reactions. 3156200100022 INC-SPECT From measurement of the fast/thermal -neutron flux 3156200100023 ratio for monitor reactions having different threshold 3156200100024 it was concluded that the neutron spectrum used was 3156200100025 approximately a fission spectrum. 3156200100026 INC-SOURCE (REAC) 3156200100027 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156200100028 activation of the target nuclei and the radioactive 3156200100029 products were identified by gamma-ray spectrometry. 3156200100030 (CHSEP) 3156200100031 DETECTOR (GELI) The radioactivity of the reaction products and 3156200100032 the monitor reactions was determined by gamma-ray 3156200100033 spectrometry using a coaxial 30 cm3 Ge(Li) detector in 3156200100034 conjunction with a 4 K Canberra Series 85 multichannel 3156200100035 analyzer. 3156200100036 PART-DET (DG) 3156200100037 CORRECTION In converting the count rates to decay rates correc- 3156200100038 tions were applied for radiochemical yields, gamma-ray 3156200100039 intensities, detector efficiencies, counting geometry, 3156200100040 absorption, self-absorption, pile-up effects and 3156200100041 coincidence losses. 3156200100042 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3156200100043 statistical and systematic errors. Main sources of 3156200100044 errors associated in cross-section measurements were 3156200100045 those associated with determination of fast neutron 3156200100046 flux densities (8%) and absolute decay rates (5 to 10%)3156200100047 Other sources of error were small and were due to 3156200100048 uncertainties in the number of target nuclei < 1% and 3156200100049 in radiation and cooling times ( 1%). 3156200100050 STATUS (TABLE) Data taken from Tabl.2 of main reference. 3156200100051 (APRVD) Entry aprroved by Dr. Jamshed Hussain Zaidi 3156200100052 HISTORY (20051214C) SD 3156200100053 (20080909A) On. According to comments from J.H.Zaidi 3156200100054 ENDBIB 52 0 3156200100055 COMMON 9 6 3156200100056 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156200100057 MONIT3-ERR MONIT4 MONIT4-ERR 3156200100058 MEV MB MB MB MB MB 3156200100059 MB B B 3156200100060 1.5 82.5 5.0 1.07 .08 113. 3156200100061 7.0 2.3 0.4 3156200100062 ENDCOMMON 6 0 3156200100063 ENDSUBENT 62 0 3156200199999 SUBENT 31562002 20051214 31183156200200001 BIB 2 2 3156200200002 REACTION (50-SN-112(N,2N)50-SN-111,,SIG,,FIS) 3156200200003 DECAY-DATA (50-SN-111,35.3MIN) 3156200200004 ENDBIB 2 0 3156200200005 NOCOMMON 0 0 3156200200006 DATA 2 1 3156200200007 DATA ERR-T 3156200200008 MB MB 3156200200009 0.12 0.01 3156200200010 ENDDATA 3 0 3156200200011 ENDSUBENT 10 0 3156200299999 SUBENT 31562003 20051214 31183156200300001 BIB 2 2 3156200300002 REACTION (50-SN-112(N,X)49-IN-111,CUM,SIG,,FIS) 3156200300003 DECAY-DATA (49-IN-111,67.0HR,DG,171.,,DG,245.) 3156200300004 ENDBIB 2 0 3156200300005 NOCOMMON 0 0 3156200300006 DATA 2 1 3156200300007 DATA ERR-T 3156200300008 MB MB 3156200300009 0.06 0.001 3156200300010 ENDDATA 3 0 3156200300011 ENDSUBENT 10 0 3156200399999 SUBENT 31562004 20051214 31183156200400001 BIB 2 2 3156200400002 REACTION (50-SN-114(N,P)49-IN-114-M,,SIG,,FIS) 3156200400003 DECAY-DATA (49-IN-114-M,49.5D) 3156200400004 ENDBIB 2 0 3156200400005 NOCOMMON 0 0 3156200400006 DATA 2 1 3156200400007 DATA ERR-T 3156200400008 MB MB 3156200400009 2.37 0.2 3156200400010 ENDDATA 3 0 3156200400011 ENDSUBENT 10 0 3156200499999 SUBENT 31562005 20051214 31183156200500001 BIB 2 2 3156200500002 REACTION (50-SN-115(N,P)49-IN-115-M,,SIG,,FIS) 3156200500003 DECAY-DATA (49-IN-115-M,4.49HR) 3156200500004 ENDBIB 2 0 3156200500005 NOCOMMON 0 0 3156200500006 DATA 2 1 3156200500007 DATA ERR-T 3156200500008 MB MB 3156200500009 0.23 0.01 3156200500010 ENDDATA 3 0 3156200500011 ENDSUBENT 10 0 3156200599999 SUBENT 31562006 20080909 31313156200600001 BIB 2 2 3156200600002 REACTION (50-SN-116(N,P)49-IN-116-G,,SIG,,FIS) 3156200600003 HISTORY (20080909A) On. SF4: -G added 3156200600004 ENDBIB 2 0 3156200600005 NOCOMMON 0 0 3156200600006 DATA 2 1 3156200600007 DATA ERR-T 3156200600008 MB MB 3156200600009 4.26 0.2 3156200600010 ENDDATA 3 0 3156200600011 ENDSUBENT 10 0 3156200699999 SUBENT 31562007 20080909 31313156200700001 BIB 2 2 3156200700002 REACTION (50-SN-117(N,P)49-IN-117-G,M+,SIG,,FIS) 3156200700003 HISTORY (20080909A) On. SF4: -G added, SF5: M+ added 3156200700004 ENDBIB 2 0 3156200700005 NOCOMMON 0 0 3156200700006 DATA 2 1 3156200700007 DATA ERR-T 3156200700008 MB MB 3156200700009 0.13 0.006 3156200700010 ENDDATA 3 0 3156200700011 ENDSUBENT 10 0 3156200799999 SUBENT 31562008 20051214 31183156200800001 BIB 1 1 3156200800002 REACTION (50-SN-118(N,A)48-CD-115-M,,SIG,,FIS) 3156200800003 ENDBIB 1 0 3156200800004 NOCOMMON 0 0 3156200800005 DATA 2 1 3156200800006 DATA ERR-T 3156200800007 MB MB 3156200800008 0.202 0.01 3156200800009 ENDDATA 3 0 3156200800010 ENDSUBENT 9 0 3156200899999 SUBENT 31562009 20080909 31313156200900001 BIB 2 2 3156200900002 REACTION (50-SN-118(N,A)48-CD-115-G,,SIG,,FIS) 3156200900003 HISTORY (20080909A) On. SF4: -G added 3156200900004 ENDBIB 2 0 3156200900005 NOCOMMON 0 0 3156200900006 DATA 2 1 3156200900007 DATA ERR-T 3156200900008 MB MB 3156200900009 0.0056 0.0002 3156200900010 ENDDATA 3 0 3156200900011 ENDSUBENT 10 0 3156200999999 SUBENT 31562010 20051214 31183156201000001 BIB 1 1 3156201000002 REACTION (50-SN-120(N,A)48-CD-117-M,,SIG,,FIS) 3156201000003 ENDBIB 1 0 3156201000004 NOCOMMON 0 0 3156201000005 DATA 2 1 3156201000006 DATA ERR-T 3156201000007 MB MB 3156201000008 0.33 0.02 3156201000009 ENDDATA 3 0 3156201000010 ENDSUBENT 9 0 3156201099999 SUBENT 31562011 20080909 31313156201100001 BIB 2 2 3156201100002 REACTION (50-SN-120(N,A)48-CD-117-G,,SIG,,FIS) 3156201100003 HISTORY (20080909A) On. SF4: -G added 3156201100004 ENDBIB 2 0 3156201100005 NOCOMMON 0 0 3156201100006 DATA 2 1 3156201100007 DATA ERR-T 3156201100008 MB MB 3156201100009 0.14 0.01 3156201100010 ENDDATA 3 0 3156201100011 ENDSUBENT 10 0 3156201199999 ENDENTRY 11 0 3156299999999