ENTRY            13027   19860402                             00001302700000001 
SUBENT        13027001   19860402                             00001302700100001 
BIB                  9         11                                 1302700100002 
INSTITUTE  (1USAPSU)                                              1302700100003 
REFERENCE  (T,SATTLER,5906)                                       1302700100004 
AUTHOR     (A.R.SATTLER)                                          1302700100005 
TITLE      AN INVESTIGATION OF THE THERMAL NEUTRON CROSS SECTION  1302700100006 
            FOR THE REACTION N14(N,P)C14 USING NUCLEAR EMULSION   1302700100007 
            TECHNIQUE.                                            1302700100008 
FACILITY   (REAC) PENN.STATE U. RESEARCH REACTOR                  1302700100009 
INC-SOURCE (THCOL)                                                1302700100010 
DETECTOR   (TRD) NUCLEAR EMULSIONS                                1302700100011 
MONITOR    (3-LI-6(N,T)2-HE-4,,SIG)                               1302700100012 
HISTORY    (860324C)                                              1302700100013 
ENDBIB              11          0                                 1302700100014 
COMMON               3          3                                 1302700100015 
EN-DUMMY   MONIT      MONIT-ERR                                   1302700100016 
EV         B          B                                           1302700100017 
 0.0253     945.       13.3                                       1302700100018 
ENDCOMMON            3          0                                 1302700100019 
ENDSUBENT           18          0                                 1302700199999 
SUBENT        13027002   19860402                             00001302700200001 
BIB                  1          1                                 1302700200002 
REACTION   (7-N-14(N,P)6-C-14,,SIG,,MXW)                          1302700200003 
ENDBIB               1          0                                 1302700200004 
NOCOMMON             0          0                                 1302700200005 
DATA                 2          1                                 1302700200006 
DATA       DATA-ERR                                               1302700200007 
B          B                                                      1302700200008 
 1.15       0.05                                                  1302700200009 
ENDDATA              3          0                                 1302700200010 
ENDSUBENT            9          0                                 1302700299999 
ENDENTRY             2          0                                 1302799999999