ENTRY            20741   19840201                             00002074100000001 
SUBENT        20741001   19840201                             00002074100100001 
BIB                 15         23                                 2074100100002 
INSTITUTE  (2GERBER)                                              2074100100003 
REFERENCE  (J,ZN/A,20,1583,6512)                                  2074100100004 
AUTHOR     (T.LAGERWALL)                                          2074100100005 
TITLE      -NEUTRON CROSS SECTIONS FOR SOME THRESHOLD REACTIONS.- 2074100100006 
INC-SOURCE (REAC ) BERLIN REACTOR.                                2074100100007 
INC-SPECT  .FAST NEUTRON FLUX.                                    2074100100008 
SAMPLE     .CRYSTAL SAMPLES OF KF, CAF(2) AND BAF(2).             2074100100009 
METHOD     (COINC) BETA-GAMMA COINCIDENCE COUNTING.               2074100100010 
DETECTOR   (SCIN ) AN ANTHRACENE AND A NAI(TL) CRYSTAL.           2074100100011 
ANALYSIS   .AFTER IRRADIATION THE TARGET-FREE ABSOLUTE ACTIVITIES 2074100100012 
            OF THE RARE GAS ISOTOPE  PRODUCTS WERE MEASURED BY    2074100100013 
            A BETA-GAMMA COINCIDENCE METHOD.                      2074100100014 
MONITOR    .THE FISSION FLUX HAS BEEN TAKEN EQUAL TO              2074100100015 
            8.7*10**11 N/CM**2*SEC(NO DETAILS FOR THIS            2074100100016 
            MEASUREMENT ARE GIVEN).                               2074100100017 
STATUS     .TAKEN FROM  Z.NATURFORSCHUNG,20A(1965)1583.           2074100100018 
HISTORY    (770425C)                                              2074100100019 
           (780307E)                                              2074100100020 
CORRECTION .FOR INTERNAL CONVERSION, FOR BREMSSTRAHLUNG, FOR      2074100100021 
            THE PRESENCE OF OTHER RARE GAS ISOTOPES.              2074100100022 
ERR-ANALYS .THE MAIN PART OF THE ERROR GIVEN IS DUE TO THE        2074100100023 
            UNCERTAINTY IN THE ABSOLUTE VALUE OF THE INTEGRATED   2074100100024 
            FISSION FLUX.                                         2074100100025 
ENDBIB              23          0                                 2074100100026 
COMMON               1          3                                 2074100100027 
EN-DUMMY                                                          2074100100028 
MEV                                                               2074100100029 
 1.5000E+00                                                       2074100100030 
ENDCOMMON            3          0                                 2074100100031 
ENDSUBENT           30          0                                 2074100199999 
SUBENT        20741002   19840201                             00002074100200001 
BIB                  1          1                                 2074100200002 
REACTION   (19-K-41(N,P)18-AR-41,,SIG,,FIS)                       2074100200003 
ENDBIB               1          0                                 2074100200004 
NOCOMMON             0          0                                 2074100200005 
DATA                 2          1                                 2074100200006 
DATA       DATA-ERR                                               2074100200007 
MB         MB                                                     2074100200008 
 2.7300E+00 4.1000E-01                                            2074100200009 
ENDDATA              3          0                                 2074100200010 
ENDSUBENT            9          0                                 2074100299999 
SUBENT        20741003   19840201                             00002074100300001 
BIB                  1          1                                 2074100300002 
REACTION   (20-CA-44(N,A)18-AR-41,,SIG,,FIS)                      2074100300003 
ENDBIB               1          0                                 2074100300004 
NOCOMMON             0          0                                 2074100300005 
DATA                 2          1                                 2074100300006 
DATA       DATA-ERR                                               2074100300007 
MB         MB                                                     2074100300008 
 6.1100E+01 9.2000E+00                                            2074100300009 
ENDDATA              3          0                                 2074100300010 
ENDSUBENT            9          0                                 2074100399999 
SUBENT        20741004   19840201                             00002074100400001 
BIB                  1          3                                 2074100400002 
REACTION   (56-BA-138(N,A)54-XE-135,,SIG,,FIS)                    2074100400003 
           .VALUE FOR THE BUILDING OF THE GROUND AND METASTABLE   2074100400004 
            STATE (INTERNAL TRANSITION 100 PER CENT).             2074100400005 
ENDBIB               3          0                                 2074100400006 
NOCOMMON             0          0                                 2074100400007 
DATA                 2          1                                 2074100400008 
DATA       DATA-ERR                                               2074100400009 
MB         MB                                                     2074100400010 
 1.9000E+00 3.0000E-01                                            2074100400011 
ENDDATA              3          0                                 2074100400012 
ENDSUBENT           11          0                                 2074100499999 
ENDENTRY             4          0                                 2074199999999