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