ENTRY            14097   20110124                             13701409700000001 
SUBENT        14097001   20110124                             13701409700100001 
BIB                 10         24                                 1409700100002 
INSTITUTE  (1USAANL,1USANWU)                                      1409700100003 
REFERENCE  (J,PR,114,1351,1959)                                   1409700100004 
AUTHOR     (A.B.Smith,P.R.Fields,R.K.Sjoblom,J.H.Roberts)         1409700100005 
TITLE      Precise Determination of the U233 Fission Neutron      1409700100006 
            Spectrum                                              1409700100007 
FACILITY   (REAC,1USAANL) CP-5 research reactor                   1409700100008 
INC-SOURCE Thermal neutron flux inducing  5E5 fission/minutes     1409700100009 
METHOD     (TOF) Fast time of flight techniques are employed      1409700100010 
            to study the neutron energy distribution from 0.3 to  1409700100011 
            5.0 Mev                                               1409700100012 
           The experimentally determined fission neutron spectrum 1409700100013 
            is expressed in the form: N(E)=(a0+a1E+a2E2)f(E),     1409700100014 
            where E is the neutron energy in Mev, N(E) is the     1409700100015 
            number of U233 fission neutrons per unit energy       1409700100016 
            interval, f(E) is the U235 prompt fission neutron     1409700100017 
            spectrum, and a0, a1, and a2 are constants normalized 1409700100018 
            to give agreement with the known average number of    1409700100019 
            U233 prompt fission neutrons                          1409700100020 
DETECTOR   (PLATE) Proton recoil emulsions are utilized for       1409700100021 
            neutron measurements from 1.2 to 7.0 Mev              1409700100022 
SAMPLE     Uranium oxide foil of 500 microg                       1409700100023 
HISTORY    (20060519C) DR                                         1409700100024 
           (20061120A) DR EN-DUMMY changed to EN                  1409700100025 
           (20101122A) OS. REACTION corrected                     1409700100026 
ENDBIB              24          0                                 1409700100027 
COMMON               1          3                                 1409700100028 
EN                                                                1409700100029 
EV                                                                1409700100030 
0.0253                                                            1409700100031 
ENDCOMMON            3          0                                 1409700100032 
ENDSUBENT           31          0                                 1409700199999 
SUBENT        14097002   20110124                             13701409700200001 
BIB                  4          4                                 1409700200002 
REACTION   (92-U-233(N,F)0-NN-1,PR,KE)                            1409700200003 
ERR-ANALYS (DATA-ERR) No information                              1409700200004 
STATUS     (TABLE) Data taken from text                           1409700200005 
HISTORY    (20101122A) OS. REACTION SF6 changed from AKE to KE    1409700200006 
ENDBIB               4          0                                 1409700200007 
NOCOMMON             0          0                                 1409700200008 
DATA                 2          1                                 1409700200009 
DATA       DATA-ERR                                               1409700200010 
MEV        MEV                                                    1409700200011 
1.870      0.04                                                   1409700200012 
ENDDATA              3          0                                 1409700200013 
ENDSUBENT           12          0                                 1409700299999 
ENDENTRY             2          0                                 1409799999999