ENTRY 22344 20121209 22342234400000001 SUBENT 22344001 20121209 22342234400100001 BIB 15 62 2234400100002 TITLE Measurement of thermal neutron cross section for 2234400100003 241-Am(n,f) reaction 2234400100004 AUTHOR (K.Kobayashi,Sh.Yamamoto,M.Miyoshi,I.Kimura,I.Kanno, 2234400100005 N.Shinohara,Y.Fujita) 2234400100006 INSTITUTE (2JPNKTO) Kobayashi,Yamamoto,Fujita - Research Reactor 2234400100007 Institute/ Miyoshi,Kimura,Kanno - Dept.of Nucl.Energy 2234400100008 (2JPNJAE) Shinohara, Dept.of Radioisotopes 2234400100009 REFERENCE ((S,JAERI-C-97-004,47,199704)= 2234400100010 (R,INDC(JPN)-178,47,199704)) main reference, data are 2234400100011 given 2234400100012 REL-REF (I,,M.Obu,S,JAERI-M-9757,1981) - fission chambers 2234400100013 (M,,K.Kanda+,J,NIM,148,535,1978) 2234400100014 FACILITY (REAC,2JPNKYO) Kyoto Univ.Reactor at Research Reactor 2234400100015 Institute 2234400100016 MONITOR (92-U-235(N,F),,SIG) 2234400100017 MONIT-REF (,,3,ENDF/B-VI,,1991) 2234400100018 R.F.Rose(Compiled and Edited), "ENDF-201, ENDF/B-VI 2234400100019 Summary Documentation", BNL-NCS-17541, 4th Ed. 2234400100020 (ENDF/B-VI) 2234400100021 INC-SOURCE (THCOL).Thermal deuterium column of 1.4 m in length 2234400100022 INC-SPECT .Neutron spectrum was measured by TOF technique and 2234400100023 may be well approximated by a Maxwellian one with 2234400100024 temperature 353 deg Kelvin (60 deg Celsius). 2234400100025 cadmium ratio is more than 5000 2234400100026 SAMPLE .Americium solution was purified by anion-exchange 2234400100027 method and then electrolysed on a stainless steel disk2234400100028 28 mm in diameter and 0.2 mm thickness, radioactive 2234400100029 area being 20 mm in diam. After electrodeposition 2234400100030 the sample was sintered with a gas burner to fix 2234400100031 the americium layer on the disk by making americium 2234400100032 oxide. Isotopic composition of Am-241 was estimated 2234400100033 as being better than 99.9%. The number of Am-241 2234400100034 atoms is (1.734+-0.020) x 10**16 2234400100035 .Highly enriched U-235 sample was prepared by the 2234400100036 electrodeposition method. Number of U-235 atoms was 2234400100037 determined to be (3.286+-0.036) x 10**17. 2234400100038 DETECTOR (FISCH) Back-to-back type fission chamber with Am-241 2234400100039 and U-235 deposits consisting of two identical 2234400100040 parallel-plate ionization chambers made of aluminium 2234400100041 and filled to 1 atm by 97% argon and 3% N2. 2234400100042 ERR-ANALYS (ERR-T) Total error consisting of standard U-235 c-s 2234400100043 error and errors given below 2234400100044 (ERR-S,0.04,0.4) statistical error 2234400100045 (ERR-1) error of assigning to Am-241 of the number 2234400100046 of fission counts 2234400100047 (ERR-2) error of assigning to U-235 of the number 2234400100048 of fission counts 2234400100049 (ERR-3) error Am-241 g-factor 2234400100050 (ERR-4) error U-235 g-factor 2234400100051 (ERR-5) error of Am-241 atoms in the sample 2234400100052 (ERR-6) error of U-235 atoms in the sample 2234400100053 (ERR-7) error of assigned setting positions of Am-241 2234400100054 and U-235 layers in the fission chamber 2234400100055 STATUS (TABLE) Data are taken from Tbl. in JAERI-C-97-004,47 2234400100056 HISTORY (19970824C) + + Compiled by S.Maev + + 2234400100057 (20101119A) SD:Updated to new date formats,lower case. 2234400100058 corrected according to last EXFOR rules and Dict. 2234400100059 Year of the ref. corrected. (1996 => 1997): 2234400100060 ((S,JAERI-97-004,47,199704)= 2234400100061 (R,INDC(JPN)-178,47,199704)) 2234400100062 (20121209U) SD: Ref. on report was corrected 2234400100063 (JAERI-97-004 -> JAERI-C-97-004). 2234400100064 ENDBIB 62 0 2234400100065 COMMON 10 6 2234400100066 EN MONIT MONIT-ERR ERR-1 ERR-2 ERR-3 2234400100067 ERR-4 ERR-5 ERR-6 ERR-7 2234400100068 EV B PER-CENT PER-CENT PER-CENT PER-CENT 2234400100069 PER-CENT PER-CENT PER-CENT PER-CENT 2234400100070 0.0253 586.2 1. 1.5 1.1 1.3 2234400100071 0. 1.2 1.1 0.25 2234400100072 ENDCOMMON 6 0 2234400100073 ENDSUBENT 72 0 2234400199999 SUBENT 22344002 20101119 22252234400200001 BIB 1 1 2234400200002 REACTION (95-AM-241(N,F),,SIG,,MXW) 2234400200003 ENDBIB 1 0 2234400200004 NOCOMMON 0 0 2234400200005 DATA 3 1 2234400200006 DATA ERR-T ERR-T 2234400200007 B B PER-CENT 2234400200008 3.15 0.097 3.1 2234400200009 ENDDATA 3 0 2234400200010 ENDSUBENT 9 0 2234400299999 ENDENTRY 2 0 2234499999999