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