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