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