ENTRY            10549   20040517                             00001054900000001 
SUBENT        10549001   20040517                             00001054900100001 
BIB                 11         20                                 1054900100002 
INSTITUTE  (1USASRL)                                              1054900100003 
REFERENCE  (J,NSE,55,24,197409)                                   1054900100004 
AUTHOR     (C.K.Paulson,E.J.Hennelly)                             1054900100005 
TITLE      Cross-Section Measurement of Plutonium-236 Formation in1054900100006 
           Plutonium-238 by 237Np(n,2n) Reactions.                1054900100007 
FACILITY   (REAC,1USASRL)                                         1054900100008 
INC-SPECT  Averaged over 235U fission spectrum above 6.8 MeV      1054900100009 
           Fraction of fission neutrons equal to or above 6.8 MeV 1054900100010 
            is 0.0168 for 235U thermal-neutron fission.           1054900100011 
METHOD     Cross section determined from the 236Pu/238Pu ratio    1054900100012 
            in low assay 238Pu, separated from irradiated fuel    1054900100013 
            assemblies.                                           1054900100014 
MONITOR    Cross section dependent upon fission spectrum accuracy 1054900100015 
ERR-ANALYS (DATA-ERR) Data error is about 10%, of which           1054900100016 
            approximately 5% is due to inaccuracies in the alpha  1054900100017 
            ratio measurement.                                    1054900100018 
STATUS     (APRVD) Approved by author 1975/12/1.                  1054900100019 
HISTORY    (19751016C)                                            1054900100020 
           (19830913A) Converted to REACTION formalism            1054900100021 
           (20040517A) Converted to new date formats, lower case. 1054900100022 
ENDBIB              20          0                                 1054900100023 
NOCOMMON             0          0                                 1054900100024 
ENDSUBENT           23          0                                 1054900199999 
SUBENT        10549002   20040517                             00001054900200001 
BIB                  1          1                                 1054900200002 
REACTION   (93-NP-237(N,2N)93-NP-236,,SIG,,FIS)                   1054900200003 
ENDBIB               1          0                                 1054900200004 
NOCOMMON             0          0                                 1054900200005 
DATA                 3          1                                 1054900200006 
EN-MIN     DATA       DATA-ERR                                    1054900200007 
MEV        MB         MB                                          1054900200008 
 6.8       63.        6.                                          1054900200009 
ENDDATA              3          0                                 1054900200010 
ENDSUBENT            9          0                                 1054900299999 
ENDENTRY             2          0                                 1054999999999