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