ENTRY            21585   20071001                             21872158500000001 
SUBENT        21585001   20071001                             21872158500100001 
BIB                 12         27                                 2158500100002 
INSTITUTE  (2JPNJAE) J.A.E.R.I. Tokai.                            2158500100003 
REFERENCE  (J,JPJ,42,(5),1773,197705)                             2158500100004 
AUTHOR     (E.Takekoshi,Y.Tsukihashi)                             2158500100005 
TITLE      -Pu-239 fission isomer in the reaction with 3-5 MeV    2158500100006 
            neutrons.-                                            2158500100007 
FACILITY   (VDG,2JPNJAE) 2 MBV Van de Graaff, period 80 micro-    2158500100008 
            seconds, pulse width 8 micro-seconds. Described       2158500100009 
            in JAERI-M-5523.                                      2158500100010 
INC-SOURCE (D-D)   1.8 MeV deuterons.                             2158500100011 
SAMPLE     .Enriched U-235 and Pu-239, 1 mg/cm**2,                2158500100012 
            1.88 cm**2 area.                                      2158500100013 
DETECTOR   (FISCH) Fission chamber at a position very close to    2158500100014 
            the neutron production target. Manufactured by AB     2158500100015 
            Atomenergi (Sweden). Covered with Cd and LI-6 + C-O3  2158500100016 
            powder to adsorb thermal neutrons in the beam         2158500100017 
PART-DET   (FF)    Fission fragments.                             2158500100018 
CORRECTION .For spontaneous fission of Pu-239.                    2158500100019 
           .For thermal neutron induced fission (estimated with   2158500100020 
            the U-235 source).                                    2158500100021 
ERR-ANALYS .No details given.                                     2158500100022 
HISTORY    (19800619C) G.C.                                       2158500100023 
           (19800718E)                                            2158500100024 
           (19821124A) Reaction string in subwork 2 corrected.    2158500100025 
           (19830111E)                                            2158500100026 
           (19840106E)                                            2158500100027 
           (20070926A) Date and SAN 002 are corrected             2158500100028 
           (20071001U) Last corrections have been done - SM       2158500100029 
ENDBIB              27          0                                 2158500100030 
NOCOMMON             0          0                                 2158500100031 
ENDSUBENT           30          0                                 2158500199999 
SUBENT        21585002   20071001                             21872158500200001 
BIB                  4         10                                 2158500200002 
REACTION   (((94-PU-239(N,INL)94-PU-239,,SIG,,SPA)+               2158500200003 
           (94-PU-239(N,F),,SIG,,SPA))/(94-PU-239(N,F),,SIG,,SPA))2158500200004 
             Averaged over broad neutron spectrum                 2158500200005 
INC-SPECT  .Neutron energy ranges from 3 to 5 MeV,                2158500200006 
            with the peak at 4.7 MeV.                             2158500200007 
STATUS     .Text, main reference.                                 2158500200008 
HISTORY    (19821124A) Reaction string corrected.                 2158500200009 
           (20071001A)  REACTION Code corrected, SF8=AV added.    2158500200010 
             RATIO to DATA, ARB-UNITS to NO-DIM changed.          2158500200011 
             SF5="PAR" in the first REACTION string deleted       2158500200012 
ENDBIB              10          0                                 2158500200013 
NOCOMMON             0          0                                 2158500200014 
DATA                 3          1                                 2158500200015 
EN-MEAN    DATA       DATA-ERR                                    2158500200016 
MEV        NO-DIM     NO-DIM                                      2158500200017 
        4.7     2.E-04     6.E-05                                 2158500200018 
ENDDATA              3          0                                 2158500200019 
ENDSUBENT           18          0                                 2158500299999 
ENDENTRY             2          0                                 2158599999999