ENTRY 41091 20160605 41764109100000001 SUBENT 41091001 20160605 41764109100100001 BIB 12 28 4109100100002 TITLE Thermal neutron fission cross-section and fission 4109100100003 resonance integral of Pu-238 4109100100004 AUTHOR (V.S.Zenkevich,Yu.A.Selitskij,V.B.Funshtein, 4109100100005 V.A.Yakovlev) 4109100100006 INSTITUTE (4RUSKUR) 4109100100007 REFERENCE ((J,YK,,(4),6,1990)=(R,INDC(CCP)-334,6,1990)) 4109100100008 (R,INDC(CCP)-365,19,1994) Engl.transl.of YK,,(4),6,19904109100100009 MONITOR (92-U-235(N,F),,RI) 4109100100010 (94-PU-239(N,F),,SIG) 4109100100011 FACILITY (REAC,4RUSKUR) F-1 reactor 4109100100012 INC-SOURCE (THCOL) 1.6E+7 n/(cm2*sec) 4109100100013 Cd ratio 600 - by U-235(n,f). 4109100100014 DETECTOR (SOLST) Mica detectors 4109100100015 For fission fragments registration. 4109100100016 SAMPLE 239Pu target with a mass of 38.3 +-0.3 ng and 4109100100017 a 235U target with a mass of 260 +- 13 ng. The weight 4109100100018 of the 235U target was determined using the alpha- 4109100100019 particle backscattering method. 4109100100020 STATUS (TABLE) Data from the text of YK,,(4),6,1990 4109100100021 ERR-ANALYS (DATA-ERR) Errors are not specified 4109100100022 HISTORY (19920427C) + + Compiled at the centre - CJD + + 4109100100023 (19931019U) / / 'MXW' added to SF8 of Subent 003 4109100100024 (20160605U) SD:Updated to new date formats,lower case. 4109100100025 Ref. YK,,(4),6,1990 -> YK,1990,(4),6=INDC(CCP)-334,6; 4109100100026 INDC(CCP)-365,19 was added. BIB update. 4109100100027 (20170710U) M.M. Previous correction of SD was 4109100100028 checked at CJD. 4109100100029 J,YK,1990,(4),6,1990 -> J,YK,,(4),6,1990 4109100100030 ENDBIB 28 0 4109100100031 NOCOMMON 0 0 4109100100032 ENDSUBENT 31 0 4109100199999 SUBENT 41091002 20160605 41764109100200001 BIB 3 7 4109100200002 REACTION (94-PU-238(N,F),,RI) 4109100200003 MONITOR (92-U-235(N,F),,RI) 4109100200004 INC-SPECT The measurement of the fission resonance integral was 4109100200005 carried out in a horizontal channel of the F-l reactor 4109100200006 in a resonance neutron flux density (1/E) of 4109100200007 1.6 x 10**7 n/(cm2*sec) and cadmium ratios 14 (by Mn-554109100200008 and Cu-63) and 30 by U-235(n,f). 4109100200009 ENDBIB 7 0 4109100200010 NOCOMMON 0 0 4109100200011 DATA 4 1 4109100200012 EN-MIN DATA DATA-ERR MONIT 4109100200013 EV B B B 4109100200014 0.5 26.3 1.5 280. 4109100200015 ENDDATA 3 0 4109100200016 ENDSUBENT 15 0 4109100299999 SUBENT 41091003 20160605 41764109100300001 BIB 4 5 4109100300002 REACTION (94-PU-238(N,F),,SIG,,MXW) 4109100300003 MONITOR (94-PU-239(N,F),,SIG,,MXW) 4109100300004 INC-SPECT The neutron flux density was 1.6 x 10**7 /cm2/s 4109100300005 with a cadmium to 235U(n,f) ratio of 600. 4109100300006 HISTORY (19931019U) 'MXW' added to SF8 in REACTION code. 4109100300007 ENDBIB 5 0 4109100300008 NOCOMMON 0 0 4109100300009 DATA 5 1 4109100300010 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 4109100300011 EV B B B B 4109100300012 0.0253 16.7 0.8 780.8 1.8 4109100300013 ENDDATA 3 0 4109100300014 ENDSUBENT 13 0 4109100399999 ENDENTRY 3 0 4109199999999