ENTRY            21216   19800918                             00002121600000001 
SUBENT        21216001   19800918                             00002121600100001 
BIB                 13         31                                 2121600100002 
INSTITUTE  (2FR BRC)                                              2121600100003 
           (3INDTRM) S.K.GUPTA.                                   2121600100004 
REFERENCE  (J,NIM,148,(1),77,7801)                                2121600100005 
AUTHOR     (S.K.GUPTA,J.FREHAUT,R.BOIS)                           2121600100006 
TITLE      -RADIATIVE CAPTURE CROSS SECTION MEASUREMENTS FOR      2121600100007 
            FAST NEUTRONS USING A LARGE GD-LOADED LIQUID          2121600100008 
            SCINTILLATOR-.                                        2121600100009 
FACILITY   (VDG  ) 4 MV PULSED VAN DE GRAAFF.                     2121600100010 
INC-SOURCE (P-T  ) THE T(P,N)HE-3 REACTION, USING A 0.8 MG/CM2    2121600100011 
            THICK TITANIUM-TRITIUM TARGET.                        2121600100012 
SAMPLE     .CHEMICALLY PURE NATURAL ELEMENTS OF AU-197 AND U-238  2121600100013 
            IN FORM OF DISCS, 2 CM IN DIAMETER AND 3 MM THICK.    2121600100014 
METHOD     (TOF  ) TIME OF FLIGHT TECHNIQUES DISCRIMINATING       2121600100015 
            BETWEEN CAPUTRE EVENTS AND OTHER EVENTS.              2121600100016 
DETECTOR   (STANK) A 100 CM DIAMETER SPHERICAL TANK, FILLED       2121600100017 
            WITH ORGANIC LIQUID SCINTILLATOR NE323, IN WHICH      2121600100018 
            0.5 PERCENT OF GADOLINIUM WAS DESOLVED.               2121600100019 
            MEASURED EFFICIENCIES ARE,                            2121600100020 
            - 80 PERCENT FOR FISSION NEUTRONS,                    2121600100021 
            - MORE THAN 95 PERCENT FOR 8 MEV GAMMA RAYS.          2121600100022 
           .A DIRCTIONAL COUNTER WAS USED TO MONITOR THE NEUTRON  2121600100023 
            FLUX.                                                 2121600100024 
STATUS     .DATA TAKEN FROM REFERENCE.                            2121600100025 
HISTORY    (791214C) CN.                                          2121600100026 
           (800115E)                                              2121600100027 
CORRECTION .THE NEUTRON FLUX MEASUREMENT HAS BEEN CORRECTED FOR   2121600100028 
            - NEUTRON ABSORPTION IN AIR                           2121600100029 
            - NEUTRON ATTENUATION IN SAMPLE                       2121600100030 
            - ENERGY DEPENDENCE OF THE MONITOR EFFICIENCY.        2121600100031 
ERR-ANALYS .THE ERRORS COME MAINLY FROM THE SUBTRACTION OF LARGE  2121600100032 
            GAMMA BACKGROUND.                                     2121600100033 
ENDBIB              31          0                                 2121600100034 
NOCOMMON             0          0                                 2121600100035 
ENDSUBENT           34          0                                 2121600199999 
SUBENT        21216002   19800115                             00002121600200001 
BIB                  4         12                                 2121600200002 
REACTION   ((92-U-238(N,G)92-U-239,,SIG)/                         2121600200003 
           (92-U-238(N,F),,SIG))                                  2121600200004 
STATUS     .DATA TAKEN FROM TEXT IN REFERENCE.                    2121600200005 
HISTORY    (791214C)                                              2121600200006 
CORRECTION .TO OBTAIN THE NEUTRON MULTIPLICITY DISTRIBUTION,      2121600200007 
            CORRECTIONS ARE APPLIED FOR,                          2121600200008 
            - TIME-DEPENDENT BACKGROUND                           2121600200009 
            - TIME-INDIPENDENT BACKGROUND                         2121600200010 
            - DEAD-TIME LOSSES                                    2121600200011 
            - NON-UNITY NEUTRON DETECTION EFFICIENCY.             2121600200012 
           .THE CAPTURE FRACTION WAS OBTAINED BY CORRECTING FOR   2121600200013 
            NEUTRON-LESS FISSION EVENTS.                          2121600200014 
ENDBIB              12          0                                 2121600200015 
NOCOMMON             0          0                                 2121600200016 
DATA                 4          1                                 2121600200017 
EN         EN-RSL     RATIO      RATIO-ERR                        2121600200018 
MEV        MEV        NO-DIM     NO-DIM                           2121600200019 
 1.9300E+00 3.0000E-02 1.0000E-01 3.0000E-02                      2121600200020 
ENDDATA              3          0                                 2121600200021 
ENDSUBENT           20          0                                 2121600299999 
SUBENT        21216003   19800115                             00002121600300001 
BIB                  5          8                                 2121600300002 
REACTION   (79-AU-197(N,G)79-AU-198-G,,SIG)                       2121600300003 
COMMENT    .DATA HAVE BEEN NORMALIZED TO THE DATA OF LINDER,      2121600300004 
            NUCL.SCI.ENG. 59 (1976) 381.                          2121600300005 
STATUS     (DEP,10221001) NORMALIZED TO DATA FROM EXFOR 10221.    2121600300006 
HISTORY    (791214C)                                              2121600300007 
CORRECTION .A CORRECTION FACTOR OF ABOUT 10 PERCENT, CALCULATED   2121600300008 
            WITH A MONTE CARLO CODE, FOR MULTIPLE SCATTERING      2121600300009 
            HAVE BEEN APPLIED.                                    2121600300010 
ENDBIB               8          0                                 2121600300011 
NOCOMMON             0          0                                 2121600300012 
DATA                 4          3                                 2121600300013 
EN         EN-RSL     DATA       DATA-ERR                         2121600300014 
MEV        MEV        MB         MB                               2121600300015 
 1.6800E+00 3.0000E-02 5.9000E+01 4.0000E+00                      2121600300016 
 1.9300E+00 3.0000E-02 5.5000E+01 4.0000E+00                      2121600300017 
 2.4400E+00 3.0000E-02 4.5000E+01 4.0000E+00                      2121600300018 
ENDDATA              5          0                                 2121600300019 
ENDSUBENT           18          0                                 2121600399999 
ENDENTRY             3          0                                 2121699999999