Measurement of thermal neutron cross section for {sup 241}Am(n,f) reaction Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.]; Miyoshi, Mitsuharu; Kimura, Itsuro; Kanno, Ikuo; Shinohara, Nobuo 66 PHYSICS; AMERICIUM 241 TARGET; NEUTRON REACTIONS; THERMAL FISSION; CROSS SECTIONS; FISSION CHAMBERS; EXPERIMENTAL DATA Making use of a standard neutron spectrum field with a pure Maxwellian distribution, the thermal neutron cross section for the {sup 241}Am(n,f) reaction has been measured relative to the reference value of 586.2b for the {sup 235U}(n,f) reaction. For the present measurement, electrodeposited layers of {sup 241}Am and {sup 235}U have been employed as back-to-back type double fission chambers. The present result at neutron energy of 0.0253 eV is 3.15 {+-} 0.097b. The ENDF/B-VI data is in good agreement with the present value, while the JENDL-3.2 data is lower by 4.2%. The evaluated data in JEF-2.2 and by Mughabghab are higher by 0.9% and 1.6%, respectively than the present result. The ratios of the earlier experimental data to the present value are distributed between 0.89 and 1.02. (author) Japan Atomic Energy Research Inst., Tokyo (Japan) OSTI as DE97758661 Japan 1997-03-01 English Technical Report Conference: ISND-1: 1. internet symposium on nuclear data, Tokai (Japan), 8 Apr - 15 Jun 1996; Other Information: PBD: Mar 1997; Related Information: Is Part Of Proceedings of the first internet symposium on nuclear data; Fukahori, Tokio; Iwamoto, Osamu; Nakagawa, Tsuneo [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment]; PB: 285 p. Medium: ED; Size: pp. 47-53 https://doi.org/ ON: DE97758661 [] JAERI-Conf-97-004; CONF-9604220-; INDC(JPN)-178/U Other: ON: DE97758661; TRN: JP9708194 JPN; SCA: 663430; 663590; PA: JPN-97:008194; EDB-97:134371; SN: 97001850446 2018-05-18 530403 https://www.osti.gov/etdeweb/servlets/purl/530403