ENTRY            13271   20200615                             147113271  0    1 
SUBENT        13271001   20200615                             147113271  1    1 
BIB                 10         18                                 13271  1    2 
TITLE      237Np fission yield of 140Ba                           13271  1    3 
AUTHOR     (R.D.Oldham,J.Williams,R.P.Larsen)                     13271  1    4 
INSTITUTE  (1USAANL)                                              13271  1    5 
REFERENCE  (P,ANL-7879,16(D),1972)                                13271  1    6 
           (P,ANL-7887,32,1971) Data for 237Np is the same as in  13271  1    7 
           the main reference. Presented 235U, 238U, and 239Pu    13271  1    8 
           fast fission yields included in 12771.                 13271  1    9 
FACILITY   (REAC,1USAANL) Assembly 61 of ZPR-3                    13271  1   10 
DETECTOR   (GELI)                                                 13271  1   11 
METHOD     (CHSEP,GSPEC)  The 237Np and 233Pa were separated by   13271  1   12 
           solvent extraction.                                    13271  1   13 
ERR-ANALYS (DATA-ERR) No information on sources of uncertainties  13271  1   14 
STATUS     (TABLE) From text (p.16) in Argonne National Laboratory13271  1   15 
                               report series, No.7879, p.16 (1972)13271  1   16 
HISTORY    (19900403C) VM                                         13271  1   17 
           (20200505U) OG. Converted to lower case and 4-digit    13271  1   18 
           year.  METHOD and REFERENCE (P,ANL-7887,32,1971) added.13271  1   19 
           ERR-ANALYS and STATUS updated.                         13271  1   20 
ENDBIB              18          0                                 13271  1   21 
NOCOMMON             0          0                                 13271  1   22 
ENDSUBENT           21          0                                 13271  199999 
SUBENT        13271002   19900406                             00001327100200001 
BIB                  1          1                                 1327100200002 
REACTION   (93-NP-237(N,F)56-BA-140,CUM,FY,,FST)                  1327100200003 
ENDBIB               1          0                                 1327100200004 
NOCOMMON             0          0                                 1327100200005 
DATA                 3          1                                 1327100200006 
EN-DUMMY   DATA       DATA-ERR                                    1327100200007 
MEV        PC/FIS     PC/FIS                                      1327100200008 
 0.4        5.41       0.20                                       1327100200009 
ENDDATA              3          0                                 1327100200010 
ENDSUBENT            9          0                                 1327100299999 
ENDENTRY             2          0                                 1327199999999