ENTRY            21476   20060809                             21782147600000001 
SUBENT        21476001   20060809                             21782147600100001 
BIB                 15         30                                 2147600100002 
INSTITUTE  (2UK HAR)                                              2147600100003 
REFERENCE  (J,JNE/AB,20,191,196603)                               2147600100004 
           (P,AERE-PR/NP-7,1,1964) ABSTRACT.                      2147600100005 
AUTHOR     (M.DE VROEY,A.T.G.FERGUSON,N.STARFELT)                 2147600100006 
TITLE      -(A MEASUREMENT OF NU-BAR FOR NEUTRON INDUCED          2147600100007 
            FISSION OF PU-240 -.                                  2147600100008 
FACILITY   (VDG  ) I.B.I.S. VAN DER GRAAFF.                       2147600100009 
INC-SOURCE (P-T  ) PULSED PROTON BEAM ON TRITIUM GAS OR           2147600100010 
            LITHIUM METAL TARGETS. PROTON ENERGY 3 MEV.           2147600100011 
SAMPLE     .FIVE MG OF PU-240 ON TWO FOILS MOUNTED BACK-TO BACK,  2147600100012 
            COMPOSITION PU-239 0.26 PC, PU-240 99.3 PC, PU-241 0. 2147600100013 
            0.3 PC.                                               2147600100014 
METHOD     (TOF  ) TIME OF FLIGHT TO DISCIMINATE BETWEEN          2147600100015 
            SPONTANEOUS AND NEUTRON INDUCED FISSION.              2147600100016 
DETECTOR   (SCIN ) PLASTIC PHOSPHOR SCINTILLATOR.                 2147600100017 
           (FISCH) FISSION CHAMBER.                               2147600100018 
MONITOR    (92-U-235(N,F),,NU) VALUE NOT GIVEN.                   2147600100019 
PART-DET   (N)     FISSION NEUTRONS.                              2147600100020 
STATUS     .TABLE 3, JNE/AB,20,191.                               2147600100021 
HISTORY    (19800327C)                                            2147600100022 
           (19800429E)                                            2147600100023 
           (20060809A) DATE and reference code corrected          2147600100024 
CORRECTION .CORRECTED FOR BACKGROUND NEUTRONS, NEUTRONS SCATTERED 2147600100025 
            FROM THE FISSION CHAMBER, THE EFFECT OF NEUTRON       2147600100026 
            FRAGMENT ANISOTROPIC DISTRIBUTIONS, FINITE FOIL       2147600100027 
            THICKNESS, AND FOR THE PRESENCE OF PU-239 AND         2147600100028 
            PU-241.                                               2147600100029 
ERR-ANALYS .ONE STANDARD DEVIATION. VALUES GIVEN ARE THE          2147600100030 
            WEIGHTED AVERAGE OF MEASUREMENTS AT VARIOUS           2147600100031 
            ANGLES.                                               2147600100032 
ENDBIB              30          0                                 2147600100033 
NOCOMMON             0          0                                 2147600100034 
ENDSUBENT           33          0                                 2147600199999 
SUBENT        21476002   20060809                             21782147600200001 
BIB                  3          5                                 2147600200002 
REACTION   (94-PU-240(N,F),,NU) NU-BAR.                           2147600200003 
STATUS     .TABLE 3.                                              2147600200004 
HISTORY    (19800327C)                                            2147600200005 
           (19800429E)                                            2147600200006 
           (20060809A)   Data units corrected                     2147600200007 
ENDBIB               5          0                                 2147600200008 
NOCOMMON             0          0                                 2147600200009 
DATA                 3          3                                 2147600200010 
EN         DATA       DATA-ERR                                    2147600200011 
MEV        PRT/FIS    PRT/FIS                                     2147600200012 
 1.0000E-01 2.8900E+00 1.9000E-01                                 2147600200013 
 1.0000E+00 2.5500E+00 3.5000E-01                                 2147600200014 
 1.6000E+00 3.2600E+00 1.2000E-01                                 2147600200015 
ENDDATA              5          0                                 2147600200016 
ENDSUBENT           15          0                                 2147600299999 
ENDENTRY             2          0                                 2147699999999