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Uncertainty analyses of neutron cross sections for Nitrogen-15, Lead-206,207,208, Bismuth-209, Plutonium-238, Americium-242m, and Curium-244 in JENDL-3.3

JENDL-3.3に収納されている$$^{15}$$N, $$^{206,207,208}$$Pb, $$^{209}$$Bi, $$^{238}$$Pu, $$^{rm 242m}$$Am, $$^{244}$$Cm中性子断面積の誤差解析

柴田 恵一; 中川 庸雄

Shibata, Keiichi; Nakagawa, Tsuneo

JENDL-3.3に収納されている$$^{15}$$N, $$^{206,207,208}$$Pb, $$^{209}$$Bi, $$^{238}$$Pu, $$^{rm 242m}$$Am, $$^{244}$$Cm中性子断面積の共分散を核変換技術開発に用いられる加速器駆動未臨界炉の設計研究のために評価した。共分散はJENDL-3.3断面積データがもとにしている実験データ及び理論計算から求められた。共分散が導出された物理量は$$^{15}$$N弾性散乱断面積,$$^{206,207,208}$$Pb及び$$^{209}$$Bi非弾性散乱断面積,$$^{238}$$Pu, $$^{rm 242m}$$Am, $$^{244}$$Cm中性子捕獲及び核分裂断面積である。$$^{238}$$Pu, $$^{rm 242m}$$Am, $$^{244}$$Cmに関しては、分離共鳴パラメータの誤差も推定した。評価結果はENDF-6フォーマットで編集され、JENDL-3.3データに組み込んだ。

Covariances of neutron cross sections for $$^{15}$$N, $$^{206,207,208}$$Pb, $$^{209}$$Bi, $$^{238}$$Pu, $$^{rm 242m}$$Am and $$^{244}$$Cm contained in JENDL-3.3 have been evaluated for the design of accelerator-driven transmutation systems. The covariances were obtained from the experimental data and model calculations on which the JENDL-3.3 data were based. The physical quantities for which covariances were deduced are the elastic scattering cross section of $$^{15}$$N, the inelastic scattering cross sections of $$^{206,207,208}$$Pb and $$^{209}$$Bi, and the fission and capture cross sections of $$^{238}$$Pu, $$^{rm 242m}$$Am and $$^{244}$$Cm. Uncertainties in the resolved resonance parameters were estimated for $$^{238}$$Pu, $$^{rm 242m}$$Am and $$^{244}$$Cm. The results were compiled in the ENDF-6 format and merged with the JENDL-3.3 data.

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パーセンタイル:53.35

分野:Nuclear Science & Technology

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