ENTRY            32819   20230905                                 3281900000001 
SUBENT        32819001   20230905   20240316                      3281900100001 
BIB                  8         12                                 3281900100002 
TITLE      Relative measurement of the mean number of prompt      3281900100003 
           neutrons from thermal neutron induced fission of       3281900100004 
           U-235 and Pu-239                                       3281900100005 
AUTHOR     (China Institute of Atomic Energy)                     3281900100006 
INSTITUTE  (3CPRAEP)                                              3281900100007 
REFERENCE  (J,CST,2,1,1960)                                       3281900100008 
FACILITY   (REAC,3CPRAEP) Heavy-water reactor                     3281900100009 
DETECTOR   (FISCH) The fission ionization chamber was made of     3281900100010 
           aluminum and was a cylinder with a length of 25 cm     3281900100011 
           and a diameter of 8.5 cm.                              3281900100012 
STATUS     (TABLE) Table 3 of At.En.Sci.Technol.2,1,1960          3281900100013 
HISTORY    (20230905C) Jimin Wang (CNDC)                          3281900100014 
ENDBIB              12          0                                 3281900100015 
NOCOMMON             0          0                                 3281900100016 
ENDSUBENT           15          0                                 3281900199999 
SUBENT        32819002   20230905   20240316                      3281900200001 
BIB                  8         15                                 3281900200002 
REACTION   ((94-PU-239(N,F),,NU)/(92-U-235(N,F),,NU))             3281900200003 
INC-SOURCE (REAC) The neutron flux was 1E6 n/cm2/s at 3000 kW     3281900200004 
SAMPLE     235U and 239Pu were electroplated onto both sides of   3281900200005 
           an aluminum foil with 0.25 mm thickness and 38 mm      3281900200006 
           diameter, the thickness 235U and 239Pu targets were    3281900200007 
           0.4 mg/cm2 and 0.1 mg/cm2.                             3281900200008 
DETECTOR   (BF3) Four CHM-8 BF3 counter                           3281900200009 
METHOD     (COINC) Detection of neutrons in slow coincidence      3281900200010 
           with fission fragments.                                3281900200011 
ERR-ANALYS (DATA-ERR) The uncertainty of measurement              3281900200012 
           (ERR-S) Statistical uncertainty, 0.7%                  3281900200013 
           (ERR-SYS,,0.2) Systematic uncertainty, <0.2%           3281900200014 
COMMENT    This result was recommend by author                    3281900200015 
STATUS     (COREL,32819003) Measurement with neutron detection    3281900200016 
           by scintillators                                       3281900200017 
ENDBIB              15          0                                 3281900200018 
COMMON               1          3                                 3281900200019 
ERR-S                                                             3281900200020 
PER-CENT                                                          3281900200021 
0.7                                                               3281900200022 
ENDCOMMON            3          0                                 3281900200023 
DATA                 3          1                                 3281900200024 
EN         DATA       DATA-ERR                                    3281900200025 
MEV        NO-DIM     NO-DIM                                      3281900200026 
   2.53E-08      1.179      0.011                                 3281900200027 
ENDDATA              3          0                                 3281900200028 
ENDSUBENT           27          0                                 3281900299999 
SUBENT        32819003   20230905   20240316                      3281900300001 
BIB                  7         13                                 3281900300002 
REACTION   ((94-PU-239(N,F),,NU)/(92-U-235(N,F),,NU))             3281900300003 
INC-SOURCE (REAC) The neutron flux was 1E8 n/cm2/s                3281900300004 
SAMPLE     235U and 239Pu were electroplated onto both sides of   3281900300005 
           an aluminum foil with 0.25 mm thickness and 38 mm      3281900300006 
           diameter, the thickness 235U and 239Pu targets were    3281900300007 
           0.5 mg/cm2 and 0.1 mg/cm2.                             3281900300008 
DETECTOR   (SCIN) The detection system consists of 6 scintillators3281900300009 
METHOD     (COINC) Detection of neutrons in fast coincidence      3281900300010 
           with fission fragments.                                3281900300011 
ERR-ANALYS (DATA-ERR) The uncertainty of measurement              3281900300012 
           (ERR-S) Statistical uncertainty, 1.3%                  3281900300013 
STATUS     (COREL,32819002) Measurement with neutron detection    3281900300014 
           by BF3 counter                                         3281900300015 
ENDBIB              13          0                                 3281900300016 
COMMON               1          3                                 3281900300017 
ERR-S                                                             3281900300018 
PER-CENT                                                          3281900300019 
1.3                                                               3281900300020 
ENDCOMMON            3          0                                 3281900300021 
DATA                 3          1                                 3281900300022 
EN         DATA       DATA-ERR                                    3281900300023 
MEV        NO-DIM     NO-DIM                                      3281900300024 
   2.53E-08      1.191      0.021                                 3281900300025 
ENDDATA              3          0                                 3281900300026 
ENDSUBENT           25          0                                 3281900399999 
ENDENTRY             3          0                                 3281999999999