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Quantifying uncertainty induced by scattering angle distribution using maximum entropy method
http://hdl.handle.net/2237/0002012806
http://hdl.handle.net/2237/0002012806fe95df69-29be-4216-a570-e1b5c669f140
| 名前 / ファイル | ライセンス | アクション |
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Download is available from 2026/9/15.
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| アイテムタイプ | itemtype_ver1(1) | |||||||||||
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| 公開日 | 2025-05-30 | |||||||||||
| タイトル | ||||||||||||
| タイトル | Quantifying uncertainty induced by scattering angle distribution using maximum entropy method | |||||||||||
| 言語 | en | |||||||||||
| 著者 |
Maruyama, Shuhei
× Maruyama, Shuhei
× Yamamoto, Akio
× Endo, Tomohiro
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| アクセス権 | ||||||||||||
| アクセス権 | embargoed access | |||||||||||
| アクセス権URI | http://purl.org/coar/access_right/c_f1cf | |||||||||||
| 権利 | ||||||||||||
| 権利情報 | © 2024. This manuscript version is made available under the CC-BY-NC-ND 4.0 license http://creativecommons.org/licenses/by-nc-nd/4.0/ | |||||||||||
| 言語 | en | |||||||||||
| 内容記述 | ||||||||||||
| 内容記述タイプ | Abstract | |||||||||||
| 内容記述 | This study developed a new method for evaluating the uncertainty in reactor core/shielding characteristics attributable to the scattering angle distribution in the combined method of the continuous energy Monte Carlo (CEMC) transport calculations and the random sampling (RS) technique based on nuclear data covariances. Recent advances in computer performance have made it possible to evaluate the nuclear data-induced uncertainty with high accuracy using the Monte Carlo method. The total Monte Carlo (TMC) method is a typical uncertainty quantification method that relies entirely on the Monte Carlo method. Another representative Monte Carlo-based uncertainty quantification method is the combination method of the RS technique based on nuclear data covariances and CEMC transport calculations (CEMC-RS). CEMC-RS has the advantage that the uncertainty can be quantified even if one is not familiar with nuclear data measurement and evaluation, as long as the nuclear data covariances are available. However, no method has been established to quantify the uncertainty in CEMC-RS, despite the fact that the uncertainty due to the scattering angle distribution is non-negligible in fast reactor core analysis and shielding analysis. This study introduces a new approach for uncertainty quantification related to scattering angle distribution in CEMC-RS, utilizing the maximum entropy method. The effectiveness of this method was verified through comparison with results from the classical deterministic uncertainty quantification approach based on generalized perturbation theory. Overall, this method offers a more accurate tool for nuclear engineers and researchers in evaluating and managing uncertainties in reactor design and safety analysis. | |||||||||||
| 言語 | en | |||||||||||
| 出版者 | ||||||||||||
| 出版者 | Elsevier | |||||||||||
| 言語 | en | |||||||||||
| 言語 | ||||||||||||
| 言語 | eng | |||||||||||
| 資源タイプ | ||||||||||||
| 資源タイプresource | http://purl.org/coar/resource_type/c_6501 | |||||||||||
| タイプ | journal article | |||||||||||
| 出版タイプ | ||||||||||||
| 出版タイプ | AM | |||||||||||
| 出版タイプResource | http://purl.org/coar/version/c_ab4af688f83e57aa | |||||||||||
| 関連情報 | ||||||||||||
| 関連タイプ | isVersionOf | |||||||||||
| 識別子タイプ | DOI | |||||||||||
| 関連識別子 | https://doi.org/10.1016/j.anucene.2024.110591 | |||||||||||
| 収録物識別子 | ||||||||||||
| 収録物識別子タイプ | PISSN | |||||||||||
| 収録物識別子 | 0306-4549 | |||||||||||
| 書誌情報 |
en : Annals of Nuclear Energy 巻 205, p. 110591, 発行日 2024-09-15 |
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| ファイル公開日 | ||||||||||||
| 日付 | 2026-09-15 | |||||||||||
| 日付タイプ | Available | |||||||||||