ENTRY            10646   20080815                             13491064600000001 
SUBENT        10646001   20080815                             13491064600100001 
BIB                 11         18                                 1064600100002 
INSTITUTE  (1USALAS)                                              1064600100003 
REFERENCE  (J,PR/C,17,385,197801)                                 1064600100004 
AUTHOR     (L.R.Veeser)                                           1064600100005 
TITLE      Prompt neutrons from neutron-induced fission of 237Np  1064600100006 
FACILITY   (VDG,1USALAS)                                          1064600100007 
INC-SOURCE (P-T). At 3 MeV and below                              1064600100008 
           (D-D). At 6.0 and 7.5 MeV                              1064600100009 
           (D-T). At 14.7 MeV                                     1064600100010 
DETECTOR   (SCIN) Gd-loaded scintillation tank                    1064600100011 
MONITOR    (98-CF-252(0,F),PR,NU) For detection efficiency.       1064600100012 
CORRECTION Corrected for fission neutrons from contaminants,      1064600100013 
            differences in 237Np and 252CF fission neutron        1064600100014 
            spectra, deadtime, and detector efficiency.           1064600100015 
STATUS     (APRVD) Approved by L. Veeser, 1978/11/20.             1064600100016 
HISTORY    (19770214C)                                            1064600100017 
           (19780808A) Published reference added with final data  1064600100018 
           (20080815A) Converted to new date formats, lower case. 1064600100019 
                       BIB update. Daya headings, units updated.  1064600100020 
ENDBIB              18          0                                 1064600100021 
NOCOMMON             0          0                                 1064600100022 
ENDSUBENT           21          0                                 1064600199999 
SUBENT        10646002   20080815                             13491064600200001 
BIB                  3         10                                 1064600200002 
REACTION   (93-NP-237(N,F),PR,NU)                                 1064600200003 
ERR-ANALYS (EN-ERR) Error due to variation of charged particle    1064600200004 
            energies in gas cell.                                 1064600200005 
           (ERR-S) Statistical uncertainty                        1064600200006 
           (DATA-ERR) Total uncertainty.Does not include          1064600200007 
            uncertainty resulting from the width of the beam      1064600200008 
            burst, anisotropy of fission fragments, effects of    1064600200009 
            delayed gamma-rays, or fission caused by low energy   1064600200010 
            neutrons (estimated small).                           1064600200011 
STATUS     (TABLE) Data taken from Table I in reference.          1064600200012 
ENDBIB              10          0                                 1064600200013 
COMMON               1          3                                 1064600200014 
MONIT                                                             1064600200015 
NO-DIM                                                            1064600200016 
 3.733                                                            1064600200017 
ENDCOMMON            3          0                                 1064600200018 
DATA                 5          6                                 1064600200019 
EN         EN-ERR     DATA       ERR-S      DATA-ERR              1064600200020 
MEV        MEV        PRT/FIS    PRT/FIS    PRT/FIS               1064600200021 
  1.0       0.11       2.718      0.057      0.063                1064600200022 
  2.0       0.08       2.934      0.057      0.064                1064600200023 
  3.0       0.06       3.037      0.056      0.064                1064600200024 
  6.0       0.13       3.495      0.052      0.063                1064600200025 
  7.5       0.09       3.856      0.055      0.067                1064600200026 
 14.7       0.15       4.785      0.071      0.085                1064600200027 
ENDDATA              8          0                                 1064600200028 
ENDSUBENT           27          0                                 1064600299999 
ENDENTRY             2          0                                 1064699999999