ENTRY 13994 20050505 13351399400000001 SUBENT 13994001 20050505 13351399400100001 BIB 10 16 1399400100002 INSTITUTE (1USALRL) 1399400100003 REFERENCE (C,82ANTWER,,218,1982) 1399400100004 AUTHOR (R.M.White,J.C.Browne) 1399400100005 TITLE Neutron-Induced Fission Cross Section Measurements and 1399400100006 Calculations of Selected Transplutonic Isotopes 1399400100007 FACILITY (LINAC,1USALRL) 1399400100008 DETECTOR (IOCH) Hemispherical ionization chamber for fission 1399400100009 fragments from 245Cm 1399400100010 (GLASD) Neutron flux measured with NE905 Li glass 1399400100011 scintillators 1399400100012 METHOD (TOF) 1399400100013 SAMPLE Sample isotopically enriched to > 99 % 245Cm 1399400100014 COMMENT Article refers to C,79KNOX,,496,1979 (13993) for the 1399400100015 data but these data are not presented in the refered 1399400100016 proceedings. 1399400100017 HISTORY (20050505C) DR 1399400100018 ENDBIB 16 0 1399400100019 NOCOMMON 0 0 1399400100020 ENDSUBENT 19 0 1399400199999 SUBENT 13994002 20050505 13351399400200001 BIB 3 3 1399400200002 REACTION (96-CM-245(N,F),,SIG) 1399400200003 ERR-ANALYS (DATA-ERR) No information 1399400200004 STATUS (CURVE) Data taken from Fig. 2 1399400200005 ENDBIB 3 0 1399400200006 NOCOMMON 0 0 1399400200007 DATA 3 66 1399400200008 EN DATA DATA-ERR 1399400200009 EV B B 1399400200010 1.096E+04 4.04E+00 2.37E-01 1399400200011 1.364E+04 3.62E+00 1.73E-01 1399400200012 1.736E+04 3.08E+00 1.44E-01 1399400200013 2.335E+04 2.90E+00 1.04E-01 1399400200014 3.188E+04 2.65E+00 9.24E-02 1399400200015 4.610E+04 2.44E+00 6.94E-02 1399400200016 5.740E+04 2.46E+00 7.52E-02 1399400200017 6.463E+04 2.30E+00 5.78E-02 1399400200018 7.435E+04 2.42E+00 6.37E-02 1399400200019 8.445E+04 2.30E+00 6.94E-02 1399400200020 9.601E+04 2.23E+00 6.35E-02 1399400200021 1.081E+05 2.11E+00 6.37E-02 1399400200022 1.173E+05 2.14E+00 4.04E-02 1399400200023 1.272E+05 2.12E+00 1399400200024 1.379E+05 2.10E+00 1399400200025 1.531E+05 2.07E+00 1399400200026 1.687E+05 2.03E+00 1399400200027 1.859E+05 2.04E+00 1399400200028 2.063E+05 1.98E+00 1399400200029 2.188E+05 2.07E+00 1399400200030 2.387E+05 1.97E+00 1399400200031 2.590E+05 1.99E+00 1399400200032 2.856E+05 2.01E+00 1399400200033 3.093E+05 1.95E+00 1399400200034 3.403E+05 1.86E+00 1399400200035 3.780E+05 1.84E+00 1399400200036 4.162E+05 1.79E+00 1399400200037 4.618E+05 1.71E+00 1399400200038 5.254E+05 1.67E+00 1399400200039 5.880E+05 1.62E+00 1399400200040 6.745E+05 1.60E+00 1399400200041 7.796E+05 1.54E+00 1399400200042 8.948E+05 1.54E+00 1399400200043 9.787E+05 1.56E+00 1399400200044 1.035E+06 1.52E+00 1399400200045 1.087E+06 1.56E+00 1399400200046 1.161E+06 1.59E+00 1399400200047 1.251E+06 1.70E+00 1399400200048 1.315E+06 1.75E+00 1399400200049 1.416E+06 1.81E+00 1399400200050 1.524E+06 1.84E+00 1399400200051 1.616E+06 1.91E+00 1399400200052 1.778E+06 1.84E+00 1399400200053 1.883E+06 1.86E+00 1399400200054 2.055E+06 1.78E+00 1399400200055 2.192E+06 1.75E+00 1399400200056 2.356E+06 1.71E+00 1399400200057 2.535E+06 1.72E+00 1399400200058 2.702E+06 1.67E+00 1399400200059 2.885E+06 1.71E+00 1399400200060 3.051E+06 1.67E+00 1399400200061 3.311E+06 1.69E+00 1399400200062 3.588E+06 1.66E+00 1399400200063 3.923E+06 1.66E+00 1399400200064 4.250E+06 1.61E+00 1399400200065 4.646E+06 1.61E+00 1399400200066 5.073E+06 1.54E+00 1399400200067 5.591E+06 1.54E+00 1399400200068 6.122E+06 1.62E+00 1399400200069 6.899E+06 1.92E+00 1399400200070 7.425E+06 1.95E+00 1399400200071 7.762E+06 2.14E+00 1399400200072 8.096E+06 2.22E+00 1399400200073 8.578E+06 2.27E+00 1399400200074 9.159E+06 2.31E+00 1399400200075 9.788E+06 2.39E+00 1399400200076 ENDDATA 68 0 1399400200077 ENDSUBENT 76 0 1399400299999 ENDENTRY 2 0 1399499999999