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