ENTRY            21596   19810408                             00002159600000001 
SUBENT        21596001   19810408                             00002159600100001 
BIB                 13         21                                 2159600100002 
INSTITUTE  (2DENRIS)                                              2159600100003 
REFERENCE  (J,RCA,23,170,77) LETTER WITH RENORMALISATION.         2159600100004 
           (R,RISO-271,17,73) REPORT OF ORIGINAL MEASURMENT.      2159600100005 
AUTHOR     (E.DAMSGAARD,K.HEYDORN,N.A.LARSEN,B.NIELSEN)           2159600100006 
TITLE      -CROSS SECTION OF THE REACTION BR-81(N,P)SE-81-M FOR   2159600100007 
            REACTOR FAST NEUTRONS -.                              2159600100008 
FACILITY   (REAC ) UNMODERATED REACTOR IRRADIATION.               2159600100009 
INC-SOURCE (REAC ) FISSION NEUTRONS.                              2159600100010 
INC-SPECT  .FISSION NEUTRON SPECTRUM. THE REACTOR                 2159600100011 
            SPECTRUM IS A REASONABLE APPROXIMATION TO A FISSION   2159600100012 
            SPECTRUM ABOVE 6 MEV IN SPITE OF A RELATIVELY HIGH    2159600100013 
            PHI(L)/PHI(S) RATIO OF 44.                            2159600100014 
METHOD     (ACTIV) ACTIVATION.                                    2159600100015 
DETECTOR   (GELI ) GAMMA DETECTION WITH GE(LI) DETECTOR.          2159600100016 
STATUS     .TEXT, RCA,23,170.                                     2159600100017 
HISTORY    (800618C)                                              2159600100018 
           (800718E)                                              2159600100019 
CORRECTION .THE NEUTRON SPECTUM APPROXIMATES TO A FISSION         2159600100020 
            SPECTRUM FOR THE REACTIONS WITH THRESHOLD NEAR        2159600100021 
            AN ENERGY OF 7 MEV.                                   2159600100022 
ERR-ANALYS .NO ERRORS GIVEN.                                      2159600100023 
ENDBIB              21          0                                 2159600100024 
COMMON               1          3                                 2159600100025 
EN-DUMMY                                                          2159600100026 
MEV                                                               2159600100027 
 1.5000E+00                                                       2159600100028 
ENDCOMMON            3          0                                 2159600100029 
ENDSUBENT           28          0                                 2159600199999 
SUBENT        21596002   19800718                             00002159600200001 
BIB                  6         15                                 2159600200002 
REACTION   (35-BR-81(N,P)34-SE-81-M,,SIG,,FIS) FISSION AVERAGE    2159600200003 
            CROSS SECTION.                                        2159600200004 
SAMPLE     .SAMPLE OF NH4BR, WITH CORRECTION FOR IMPURITY         2159600200005 
            OF SE. SIMULATANEOUS IRRADIATION OF SE ANF NH4BR      2159600200006 
            WITH AND WITHOUT CD ABSORBERS. THIS METHOD            2159600200007 
            COMPENSATES FOR THE EFFECT OF EPITHERMAL NEUTRONS     2159600200008 
            AND FOR MODERATION OF FAST NEUTRONS IN THE TARGET     2159600200009 
            MATERIALS.                                            2159600200010 
DECAY-DATA (34-SE-81-M,57.3MIN,DG)                                2159600200011 
MONITOR    (34-SE-80(N,G)34-SE-81-M,,SIG,,MXW) THERMAL            2159600200012 
            NEUTRON CAPTURE CROSS SECTION. VALUE TAKEN FROM       2159600200013 
            THE COMPILATION OF SHER, IAEA, 1974.                  2159600200014 
STATUS     .TABLE IN RCA,23,170.                                  2159600200015 
HISTORY    (800618C)                                              2159600200016 
           (800718E)                                              2159600200017 
ENDBIB              15          0                                 2159600200018 
NOCOMMON             0          0                                 2159600200019 
DATA                 4          1                                 2159600200020 
EN-NRM     MONIT      MONIT-ERR  DATA                             2159600200021 
EV         MB         MB         MB                               2159600200022 
 2.5300E-02 8.0000E+01 1.0000E+01 3.6800E-02                      2159600200023 
ENDDATA              3          0                                 2159600200024 
ENDSUBENT           23          0                                 2159600299999 
SUBENT        21596003   19810408                             00002159600300001 
BIB                  5          8                                 2159600300002 
REACTION   (26-FE-56(N,P)25-MN-56,,SIG,,FIS) FISSION              2159600300003 
            SPECTRUM AVERAGE CROSS SECTION.                       2159600300004 
SAMPLE     .NO DETAILS.                                           2159600300005 
COMMENT    .THIS MEASUREMENT IS A CHECK OF THE NEUTRON SPECTRUM   2159600300006 
            USED IN MEASUREMENT OF THE BR-81(N,P) CROSS SECTION   2159600300007 
STATUS     .TEXT, PAGE 171.                                       2159600300008 
HISTORY    (800618C)                                              2159600300009 
           (800718E)                                              2159600300010 
ENDBIB               8          0                                 2159600300011 
NOCOMMON             0          0                                 2159600300012 
DATA                 2          1                                 2159600300013 
DATA       DATA-ERR                                               2159600300014 
MB         MB                                                     2159600300015 
 1.0400E+00 3.0000E-02                                            2159600300016 
ENDDATA              3          0                                 2159600300017 
ENDSUBENT           16          0                                 2159600399999 
ENDENTRY             3          0                                 2159699999999