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