ENTRY 41355 20091216 41484135500000001
SUBENT 41355001 20091216 41484135500100001
BIB 13 30 4135500100002
TITLE .Measurements of Delayed Neutron Yield on Thermal 4135500100003
Neutron Induced Fission of 237Np Using Cross- 4135500100004
Correlation Technique 4135500100005
AUTHOR (Sh.S.Zeinalov, O.V.Zeinalova, V.I.Smirnov) 4135500100006
INSTITUTE (4ZZZDUB) 4135500100007
REFERENCE ((S,ISINN-7,348,1999)=(S,JINR-E3-99-212,348,1999)) 4135500100008
On irst page there is a misprint in report number 4135500100009
E3-98-212 instead of E3-99-212 as on last page. 4135500100010
REL-REF (N,,S.B.Borzakov+,R,JINR-E3-98-145,1998) Experimental 4135500100011
details 4135500100012
FACILITY (REAC) IBR-2 Fast Pulse Reactor. Pulse repetition 4135500100013
rate is 5 Hz, mean power of reactor 1.5 MW. 4135500100014
(CHOPS) Slow neutron chopper which modulates neutron 4135500100015
beam and allows cross-correlation analysis 4135500100016
of emitted delayed neutrons 4135500100017
INC-SOURCE (REAC) Bent mirror neutron guide. Cadmium sheet 4135500100018
was used to cut slow neutrons 4135500100019
DETECTOR (PROPC) 12 He-3 counters placed in 450*450*450 cm 4135500100020
poyethilene cube . 4135500100021
Ratio of detector efficiencies of prompt to delayed 4135500100022
neutrons was found in calibration procedure with U-235.4135500100023
MONITOR (92-U-235(N,F),PR,NU) 4135500100024
INC-SPECT Thermal neutrons. Mean value of thermal neutron flux 4135500100025
at the sample 4.0E+4 n/s/cm**2 4135500100026
ERR-ANALYS (DATA-ERR) Not specified 4135500100027
STATUS (TABLE) Data from text of S,ISINN-7,348,1999, page 353.4135500100028
HISTORY (20000320C) + + Compiled at the CJD 4135500100029
(20000320U) Last checking has been done. 4135500100030
(20091216U) Reference S,ISINN-7 was added. 4135500100031
BIB information was added. 4135500100032
ENDBIB 30 0 4135500100033
COMMON 1 3 4135500100034
EN-DUMMY 4135500100035
EV 4135500100036
2.53E-02 4135500100037
ENDCOMMON 3 0 4135500100038
ENDSUBENT 37 0 4135500199999
SUBENT 41355002 20091216 41484135500200001
BIB 2 4 4135500200002
REACTION ((93-NP-237(N,F),DL,NU)/(93-NP-237(N,F),,NU)) 4135500200003
ANALYSIS Ratio NUd/NUp was obtained from cross-correlation 4135500200004
functions for three groups of neutrons reduced to one 4135500200005
period - prompt, delayed, fast. 4135500200006
ENDBIB 4 0 4135500200007
NOCOMMON 0 0 4135500200008
DATA 2 1 4135500200009
DATA DATA-ERR 4135500200010
NO-DIM NO-DIM 4135500200011
4.6E-03 2.E-04 4135500200012
ENDDATA 3 0 4135500200013
ENDSUBENT 12 0 4135500299999
SUBENT 41355003 20091216 41484135500300001
BIB 5 6 4135500300002
REACTION (93-NP-237(N,F),DL,NU,,,DERIV) 4135500300003
ANALYSIS Obtained from measured value of NUd/NUp. 4135500300004
REL-REF (R,21651003,H.Thierens+,J,NP/A,342,(2),229,198006) 4135500300005
STATUS (DEP,41355002) 4135500300006
(DEP,21651003) 4135500300007
HISTORY (20091216U) Units were changed: PART/FIS -> PRT/FIS. 4135500300008
ENDBIB 6 0 4135500300009
NOCOMMON 0 0 4135500300010
DATA 2 1 4135500300011
DATA DATA-ERR 4135500300012
PRT/FIS PRT/FIS 4135500300013
1.14E-02 9.E-04 4135500300014
ENDDATA 3 0 4135500300015
ENDSUBENT 14 0 4135500399999
ENDENTRY 3 0 4135599999999