ENDF/B-VII.1 nuclear data for science and technology; Cross sections, covariances, fission product yields and decay data

科学と技術のための核データENDF/B-VII.1; 断面積,共分散,核分裂収率及び崩壊データ

Chadwick, M. B.*; Herman, M.*; Obloinsk, P.*; Dunn, M. E.*; Danon, Y.*; Kahler, A. C.*; Smith, D. L.*; Pritychenko, B.*; Arbanas, G.*; Arcilla, R.*; Brewer, R.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Cho, Y. S.*; Derrien, H.*; Guber, K.*; Hale, G. M.*; Hoblit, S.*; Holloway, S.*; Johnson, T. D.*; 河野 俊彦*; Kiedrowski, B. C.*; Kim, H.*; 国枝 賢  ; Larson, N. M.*; Leal, L.*; Lestone, J. P.*; Little, R. C.*; McCutchan, E. A.*; MacFarlane, R. E.*; MacInnes, M.*; Mattoon, C. M.*; McKnight, R. D.*; Mughabghab, S. F.*; Nobre, G. P. A.*; Palmiotti, G.*; Palumbo, A.*; Pigni, M. T.*; Pronyaev, V. G.*; Sayer, R. O.*; Sonzogni, A. A.*; Summers, N. C.*; Talou, P.*; Thompson, I. J.*; Trkov, A.*; Vogt, R. L.*; Van der Marck, S. C.*; Wallner, A.*; White, M. C.*; Wiarda, D.*; Young, P. G.*

Chadwick, M. B.*; Herman, M.*; Obloinsk, P.*; Dunn, M. E.*; Danon, Y.*; Kahler, A. C.*; Smith, D. L.*; Pritychenko, B.*; Arbanas, G.*; Arcilla, R.*; Brewer, R.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Cho, Y. S.*; Derrien, H.*; Guber, K.*; Hale, G. M.*; Hoblit, S.*; Holloway, S.*; Johnson, T. D.*; Kawano, Toshihiko*; Kiedrowski, B. C.*; Kim, H.*; Kunieda, Satoshi; Larson, N. M.*; Leal, L.*; Lestone, J. P.*; Little, R. C.*; McCutchan, E. A.*; MacFarlane, R. E.*; MacInnes, M.*; Mattoon, C. M.*; McKnight, R. D.*; Mughabghab, S. F.*; Nobre, G. P. A.*; Palmiotti, G.*; Palumbo, A.*; Pigni, M. T.*; Pronyaev, V. G.*; Sayer, R. O.*; Sonzogni, A. A.*; Summers, N. C.*; Talou, P.*; Thompson, I. J.*; Trkov, A.*; Vogt, R. L.*; Van der Marck, S. C.*; Wallner, A.*; White, M. C.*; Wiarda, D.*; Young, P. G.*

原子力科学・技術の利用分野ための評価済み核データライブラリーENDF/B-VII.1を公開した。米国核データ評価委員会が中心となって評価・整備したこの最新ライブラリーは、前バージョン(ENDF/B-VII.0)公開以後に得られた原子核理論や実験に関する知見を反映した中性子断面積,共分散,核分裂収率や崩壊データ等を格納している。ライブラリーの主な更新内容は、核種数の拡大、共分散データの拡充、R行列理論に基づく軽核の共鳴パラメータ評価、中重核やアクチノイドデータの改訂等である。核外輸送コードMCNPによるベンチマーク解析を行った結果、臨界予測性能等のパフォーマンスが向上した。

The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. It features extension of covered nuclei, covariance data for 190 nuclei, R-matrix analyses of neutron reactions on light nuclei, updates for some medium-heavy and actinoid nuclei, etc. Criticality benchmark tests with a transport simulation code MCNP shows improved performances.