ENTRY            10222   20120512                             13811022200000001 
SUBENT        10222001   20120512                             13811022200100001 
BIB                 13         18                                 1022200100002 
INSTITUTE  (1USAORL)                                              1022200100003 
REFERENCE  (P,ORNL-4706,53,197105)                                1022200100004 
AUTHOR     (J.Halperin,J.H.Oliver,R.W.Stoughton)                  1022200100005 
TITLE      The thermal cross section and resonance integral       1022200100006 
           for neutron fission of 252Cf                           1022200100007 
FACILITY   (REAC,1USAORL) Oak Ridge Research Reactor              1022200100008 
INC-SOURCE (REAC)                                                 1022200100009 
INC-SPECT   Thermal and epithermal reactor spectrum               1022200100010 
DETECTOR   (TRD) Polycarbonate plastic film and muscovite         1022200100011 
            for filtered and unfiltered irradiations.             1022200100012 
PART-DET   (FF) Fission tracks counted                            1022200100013 
ANALYSIS   Weighted average from twelve measurements.             1022200100014 
ERR-ANALYS (DATA-ERR) No information on source of uncertainty.    1022200100015 
STATUS     (PRELM). Data taken from tables in reference.          1022200100016 
HISTORY    (19710501)                                             1022200100017 
           (19821014A) Converted to REACTION formalism            1022200100018 
           (20010309A) Updated to new date formats, lower case.   1022200100019 
           (20120130U) SD: page added to ref.                     1022200100020 
ENDBIB              18          0                                 1022200100021 
NOCOMMON             0          0                                 1022200100022 
ENDSUBENT           21          0                                 1022200199999 
SUBENT        10222002   20010309                             00001022200200001 
BIB                  1          1                                 1022200200002 
REACTION   (98-CF-252(N,F),,SIG,,MXW)                             1022200200003 
ENDBIB               1          0                                 1022200200004 
NOCOMMON             0          0                                 1022200200005 
DATA                 3          1                                 1022200200006 
EN-DUMMY   DATA       DATA-ERR                                    1022200200007 
EV         B          B                                           1022200200008 
0.025      32.0       4.0                                         1022200200009 
ENDDATA              3          0                                 1022200200010 
ENDSUBENT            9          0                                 1022200299999 
SUBENT        10222003   20010309                             00001022200300001 
BIB                  1          1                                 1022200300002 
REACTION   (98-CF-252(N,F),,RI)                                   1022200300003 
ENDBIB               1          0                                 1022200300004 
NOCOMMON             0          0                                 1022200300005 
DATA                 3          1                                 1022200300006 
EN-MIN     DATA       DATA-ERR                                    1022200300007 
EV         B          B                                           1022200300008 
0.054      110.0      30.0                                        1022200300009 
ENDDATA              3          0                                 1022200300010 
ENDSUBENT            9          0                                 1022200399999 
ENDENTRY             3          0                                 1022299999999