ENTRY 30536 20120518 31553053600000001 SUBENT 30536001 20120518 31553053600100001 BIB 10 27 3053600100002 INSTITUTE (3CPRAEP) 3053600100003 REFERENCE (J,CNP,1,(1),9,1979) 3053600100004 AUTHOR (Zhang Huan-Qiao,Liu Zu-Hua) 3053600100005 TITLE The measurement of the average number of prompt 3053600100006 neutrons and the distribution of prompt neutron numbers3053600100007 for Cf-252 spontaneous fission. 3053600100008 SAMPLE No detail information. 3053600100009 METHOD Liquid-scintillation method. 3053600100010 DETECTOR (STANK) 3053600100011 111 Litre of toluen-based gadolinium-loaded 3053600100012 scintillation liquid filled in a spherical aluminum 3053600100013 container with a diameter of 60 cm. 3053600100014 6 Photo-multipliers EMI9530B were used. 3053600100015 .Neutron detection efficiency of liquid scintillator 3053600100016 was calculated by Monte Carlo calculation code, 3053600100017 written by Xu Shu-Yan et al.,J.Nucl.Sci.Tech.(to be 3053600100018 published). 3053600100019 .Spontaneous fission events were detected by fast 3053600100020 current ionization chamber. 3053600100021 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 3053600100022 STATUS (TABLE) Data taken from Chinese 3053600100023 J.Nucl.Phys.Vol.1,No1,(1979)9. 3053600100024 HISTORY (19800328C) KO. 3053600100025 (19850215U) OS. Country code corrected. 3053600100026 (20090312A) SD:Updated to new date formats,lower case, 3053600100027 made formal corrections. 3053600100028 (20120504A) VS. INC-SOURCE deleted. 3053600100029 ENDBIB 27 0 3053600100030 NOCOMMON 0 0 3053600100031 ENDSUBENT 30 0 3053600199999 SUBENT 30536002 20090321 31373053600200001 BIB 3 24 3053600200002 REACTION (98-CF-252(0,F),PR,NU) 3053600200003 COMMENT The final detection efficiency for the neutrons from 3053600200004 spontaneous fission of Cf-252 is 0.5818 +- 0.0022. 3053600200005 ERR-ANALYS (DATA-ERR) Corrections and errors in efficiency 3053600200006 and Nu(pr) are following. 3053600200007 ** Efficiency ** 3053600200008 Correction(%) Relative error(%) 3053600200009 Counting statistics +- 0.10 3053600200010 Pulse pile-up 0.3 +- 0.06 3053600200011 Crystal end effect -0.04 +- 0.008 3053600200012 Scattering by carbon -0.4 +- 0.08 3053600200013 Proton multiple scat. -0.5 +- 0.1 3053600200014 Fission n-spectrum +- 0.23 3053600200015 Anisotroric effect -1.75 +- 0.26 3053600200016 == Sum == -2.39 +- 0.388 3053600200017 ** Spontaneous fission ** 3053600200018 Correction(%) Relative error(%) 3053600200019 Counting statistics +- 0.15 3053600200020 Pulse pile-up 1.02 +- 0.10 3053600200021 False gate 0. 0. 3053600200022 Efficiency +2.39 +- 0.388 3053600200023 Delay gamma-rays -0.3 +- 0.07 3053600200024 French effect -0.39 +- 0.2 3053600200025 == Sum == +2.7 +- 0.48 3053600200026 ENDBIB 24 0 3053600200027 NOCOMMON 0 0 3053600200028 DATA 2 1 3053600200029 DATA DATA-ERR 3053600200030 PRT/FIS PRT/FIS 3053600200031 3.7430E+00 1.8000E-02 3053600200032 ENDDATA 3 0 3053600200033 ENDSUBENT 32 0 3053600299999 ENDENTRY 2 0 3053699999999