ENTRY 30631 20060315 31193063100000001 SUBENT 30631001 20060315 31193063100100001 BIB 13 52 3063100100002 INSTITUTE (3INDTRM) 3063100100003 REFERENCE (J,RCA,30,11,1982) Final results 3063100100004 (R,BARC-1126,7,1981) The same data as in RCA,30,11,82 3063100100005 AUTHOR (A.Ramaswami,K.Raghuraman,B.K.Srivastava,R.H.Iyer) 3063100100006 TITLE Absolute yields of fission products in the thermal- 3063100100007 neutron induced fission of 245Cm 3063100100008 FACILITY (REAC) Natural uranium heavy water reactor cirus 3063100100009 with neutron flux 1*10**13 n/cm**2/sec 3063100100010 INC-SPECT Predominantly thermal 3063100100011 SAMPLE The isotopic composition was (in atom percentage) 3063100100012 96-Cm-244 - 93.86% 3063100100013 96-Cm-245 - 2.01% 3063100100014 96-Cm-246 - 4.13% 3063100100015 Samples were prepared by evaporating a known weight of 3063100100016 the solution of curium (about 100 microgramm) in 3063100100017 dilute nitric acid on super pure aluminium foils 3063100100018 since 245Cm has a thermal neutron cross-section 3063100100019 about 1924 times higher than that of 244Cm, 99% 3063100100020 of the total fission in the thermal neutron 3063100100021 irradiation will be from 245Cm 3063100100022 METHOD Track-etch-cum gamma-ray spectrometric technique 3063100100023 (see A.Ramaswami et al.,J.Inorg.Nucl.Chem.,41(1979) 3063100100024 1531, ibid.42(1980)1213) 3063100100025 DETECTOR (TRD) A mica strip track detector for registration 3063100100026 of the number of the fission events occuring in the 3063100100027 sample 3063100100028 (GELI) 60. c.c. Ge(Li) Detector for determination 3063100100029 of the number of the fission product atoms 3063100100030 DECAY-DATA ((1.)38-SR-91,9.48HR,DG,1024.3,0.335) 3063100100031 ((2.)38-SR-92,2.71HR,DG,1383.9,0.9) 3063100100032 ((3.)40-ZR-97,17.0HR,DG,743.4,0.9796) 3063100100033 ((4.)42-MO-99,66.6HR,DG,140.5,0.907) 3063100100034 ((5.)44-RU-105,4.4HR,DG,724.3,0.48) 3063100100035 ((6.)45-RH-105-G,35.36HR,DG,318.9,0.192) 3063100100036 ((7.)53-I-131,8.05D,DG,364.5,0.825) 3063100100037 ((8.)52-TE-132,3.28D,DG,228.3,0.882) 3063100100038 ((9.)53-I-133-G,20.8HR,DG,529.97,0.873) 3063100100039 ((10.)54-XE-135-G,9.15HR,DG,249.8,0.90) 3063100100040 ((11.)55-CS-138-G,32.2MIN,DG,1435.9,0.763) 3063100100041 ((12.)56-BA-140,12.79D,DG,537.6,0.244) 3063100100042 ((13.)57-LA-142,93.3MIN,DG,641.29,0.525) 3063100100043 ((14.)58-CE-143,32.7HR,DG,293.3,0.434) 3063100100044 STATUS Data from tables 2 and 3 of the first reference 3063100100045 HISTORY (19820630C) Data compiled. VP. 3063100100046 (20040311U) SD: corrected 4-dig. year and lower cases. 3063100100047 (20060314U) page corrected in ref. 3063100100048 ERR-ANALYS (ERR-S) Statistical error on number of counts 3063100100049 (ERR-1) Error on gamma-ray intensity 3063100100050 (ERR-2) Error on number of fission 3063100100051 (ERR-3) Error on values of gamma-ray detection 3063100100052 efficiency 3063100100053 (ERR-T) Total error 3063100100054 ENDBIB 52 0 3063100100055 NOCOMMON 0 0 3063100100056 ENDSUBENT 55 0 3063100199999 SUBENT 30631002 19840912 00003063100200001 BIB 1 1 3063100200002 REACTION (96-CM-245(N,F)ELEM/MASS,CUM,FY,,MXW) 3063100200003 ENDBIB 1 0 3063100200004 COMMON 1 3 3063100200005 EN-DUMMY 3063100200006 EV 3063100200007 2.5300E-02 3063100200008 ENDCOMMON 3 0 3063100200009 DATA 9 14 3063100200010 MASS ELEMENT DATA ERR-S ERR-1 ERR-2 3063100200011 ERR-3 ERR-T DECAY-FLAG 3063100200012 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 3063100200013 PER-CENT PER-CENT NO-DIM 3063100200014 9.1000E+01 3.8000E+01 9.8000E-01 3.1000E+00 2.0000E+00 5.0000E+003063100200015 3.0000E+00 6.9000E+00 1.0000E+00 3063100200016 9.2000E+01 3.8000E+01 1.2800E+00 7.8000E+00 1.1000E+01 5.0000E+003063100200017 3.0000E+00 1.4700E+01 2.0000E+00 3063100200018 9.7000E+01 4.0000E+01 2.4000E+00 2.1000E+00 6.0000E-02 5.0000E+003063100200019 3.0000E+00 6.2000E+00 3.0000E+00 3063100200020 9.9000E+01 4.2000E+01 4.0500E+00 5.0000E-01 7.0000E-01 5.0000E+003063100200021 3.0000E+00 5.9000E+00 4.0000E+00 3063100200022 1.0500E+02 4.4000E+01 6.3900E+00 1.0000E+00 2.0000E+00 5.0000E+003063100200023 3.0000E+00 6.3000E+00 5.0000E+00 3063100200024 1.0500E+02 4.5000E+01 5.8900E+00 1.0000E+00 1.0000E+00 5.0000E+003063100200025 3.0000E+00 6.0000E+00 6.0000E+00 3063100200026 1.3100E+02 5.3000E+01 2.7800E+00 1.4000E+00 5.0000E-01 5.0000E+003063100200027 3.0000E+00 6.0000E+00 7.0000E+00 3063100200028 1.3200E+02 5.2000E+01 3.7900E+00 8.0000E-01 2.2000E-01 5.0000E+003063100200029 3.0000E+00 5.9000E+00 8.0000E+00 3063100200030 1.3300E+02 5.3000E+01 5.2800E+00 7.5000E-01 2.2000E-01 5.0000E+003063100200031 3.0000E+00 5.9000E+00 9.0000E+00 3063100200032 1.3500E+02 5.4000E+01 6.4500E+00 9.0000E-01 3.3000E+00 5.0000E+003063100200033 3.0000E+00 6.8000E+00 1.0000E+01 3063100200034 1.3800E+02 5.5000E+01 5.9000E+00 1.7000E+00 2.1000E+00 5.0000E+003063100200035 3.0000E+00 6.4000E+00 1.1000E+01 3063100200036 1.4000E+02 5.6000E+01 5.4100E+00 1.1000E+00 8.2000E-01 5.0000E+003063100200037 3.0000E+00 6.0000E+00 1.2000E+01 3063100200038 1.4200E+02 5.7000E+01 4.5900E+00 3.3000E+00 4.8000E+00 5.0000E+003063100200039 3.0000E+00 8.3000E+00 1.3000E+01 3063100200040 1.4300E+02 5.8000E+01 4.2800E+00 9.0000E-01 4.6000E+00 5.0000E+003063100200041 3.0000E+00 7.5000E+00 1.4000E+01 3063100200042 ENDDATA 32 0 3063100200043 ENDSUBENT 42 0 3063100299999 ENDENTRY 2 0 3063199999999