ENTRY 23115 20151013 22452311500000001 SUBENT 23115001 20151013 22452311500100001 BIB 14 23 2311500100002 TITLE Thermal neutron-induced fission cross sections of Cm 2311500100003 isotopes. 2311500100004 AUTHOR (L.Popescu, J.Heyse, J.Wagemans, C.Wagemans) 2311500100005 INSTITUTE (2BLGMOL) L.Popescu, J.Heyse, J.Wagemans 2311500100006 (2BLGGHT) C.Wagemans 2311500100007 REFERENCE (S,AIP-1175,401,2009) 2311500100008 Proc.of Int.Workshop on Nuclear Fission and 2311500100009 Fission-product spectroscopy. 2311500100010 Main reference. 2311500100011 REL-REF (R,,S.F.Mughabghab,B,NEUT.RES,,2006) 2311500100012 EXP-YEAR (2008) November 2008. 2311500100013 FACILITY (REAC,2BLGMOL) Graphite moderated BR1 reactor. 2311500100014 INC-SOURCE (REAC) Neutron beam is collimated to diameter of 20 mm 2311500100015 INC-SPECT Well thermalized neutron beam. 2311500100016 MONITOR (5-B-10(N,A)3-LI-7,,SIG) 2311500100017 For neutron flux normalization. 2311500100018 ((MONIT)92-U-235(N,F),,SIG) at En=25.3 milli-eV. 2311500100019 MONIT-REF ((MONIT),S.F.Mughabghab,B,NEUT.RES,,2006) 2311500100020 DETECTOR (SIBAR) Two surface barrier detectors to detect 2311500100021 fission fragments from Cm and alphas from monitor. 2311500100022 METHOD (PHD) 2311500100023 HISTORY (20101105C) M.M. 2311500100024 (20151013U) SD: Year of publ. corrected (2010 -> 2009).2311500100025 ENDBIB 23 0 2311500100026 NOCOMMON 0 0 2311500100027 ENDSUBENT 26 0 2311500199999 SUBENT 23115002 20101104 22232311500200001 BIB 6 33 2311500200002 REACTION (96-CM-245(N,F),,SIG) 2311500200003 SAMPLE Two sample were mounted in the center of vacuum clamber2311500200004 back-to-back on support plate. 2311500200005 B-10 sample - to monitor neutron beam by (n,alpha) . 2311500200006 Cm-oxide sample of 141+-3 microg, deposited on Al 2311500200007 30 microm backing, of 15 mm diameter. 2311500200008 Isotopic composition: 2311500200009 Isotope Number of Atoms At.% 2311500200010 Cm-244 3.11x10**15 0.901 2311500200011 Cm-245 3.41x10**17 98.685 2311500200012 Cm-246 1.40x10**15 0.404 2311500200013 Cm-247 2.75x10**15 0.008 2311500200014 Cm-248 6.85x10**15 0.002 2311500200015 U-235 99.94% enriched sample, with a diameter of 15 mm 2311500200016 ,mass of (193.29+1.33)microg, deposited on a 30 microm 2311500200017 thick Al backing; used to determine neutron flux and 2311500200018 detection efficiency. 2311500200019 ANALYSIS Deviation of a 1/v behavior is given by the so-called 2311500200020 Westcott factor, which depends on the temperature of 2311500200021 the neutron spectrum. The Westcott factors for U-235 = 2311500200022 0.9772+0.0008 and for Cm-245 = 0.954+0.033 were used 2311500200023 from REL-REF of S.F.Mughabghab. 2311500200024 Our result overlaps within the error bars with the 2311500200025 previous results and it shows a deviation of about 6% 2311500200026 from the value adopted by the nuclear data libraries. 2311500200027 CORRECTION For 1.6% contribution from SF to the spectrum. 2311500200028 For 2.6% contribution from the epithermal component to 2311500200029 the (n,f) spectrum. 2311500200030 ERR-ANALYS (ERR-1) Uncertainty due to Cm-245 Westcott factor. 2311500200031 (ERR-S) Statistical uncertainty 0.9 %. 2311500200032 (ERR-SYS) Systematical uncertainty 4.1% . 2311500200033 STATUS (TABLE) Text, page 403 of S,AIP-1175,,401,2010. 2311500200034 (PRELM) Preliminary result. 2311500200035 ENDBIB 33 0 2311500200036 COMMON 3 3 2311500200037 EN MONIT ERR-1 2311500200038 MILLI-EV B PER-CENT 2311500200039 25.3 582.60 3.5 2311500200040 ENDCOMMON 3 0 2311500200041 DATA 3 1 2311500200042 DATA ERR-S ERR-SYS 2311500200043 B B B 2311500200044 1951. 18. 81. 2311500200045 ENDDATA 3 0 2311500200046 ENDSUBENT 45 0 2311500299999 ENDENTRY 2 0 2311599999999