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Bias factor method using random sampling technique
http://hdl.handle.net/2237/25271
http://hdl.handle.net/2237/252714caaf36b-409c-4a49-b46c-110dc21c98f8
名前 / ファイル | ライセンス | アクション |
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JNST53_10_pp1494-1501_2016.pdf ファイル公開:2017/01/08 (782.5 kB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2016-12-20 | |||||
タイトル | ||||||
タイトル | Bias factor method using random sampling technique | |||||
言語 | en | |||||
著者 |
Endo, Tomohiro
× Endo, Tomohiro× Yamamoto, Akio× Watanabe, Tomoaki |
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アクセス権 | ||||||
アクセス権 | open access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_abf2 | |||||
権利 | ||||||
言語 | en | |||||
権利情報 | This is an Accepted Manuscript of an article published by Taylor & Francis Group in Journal of Nuclear Science and Technology on 08/01/2016, available online: http://www.tandfonline.com/10.1080/00223131.2015.1126541 | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Bias factor method | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | random sampling | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | bootstrap method | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | bias | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | uncertainty | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | covariance | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | correlation | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | numerical analysis | |||||
抄録 | ||||||
内容記述 | Toward the practical use of the bias factor method for actual light water reactor core analyses, the bias factor method using the random sampling technique is newly proposed. The bias factor method is one of the correction methods using information of E/C values in existing measurable systems, to reduce biases and uncertainties of predicted core characteristics parameters. By the aid of the random sampling technique, our proposed bias factor method can be carried out using only forward calculations without any adjoint calculations, and can easily take into account burnup and thermal-hydraulic feedback effects, which are difficult points in the practical application to actual core analyses. Although the statistical error due to the random sampling technique is inevitable in the proposed method, the statistical error can be simply quantified by the resampling technique such as the bootstrap method. As one of the feasibility studies, effectiveness of the proposed method is verified through a numerical experiment which virtually simulates a typical equilibrium pressurized water reactor core. In this verification problem, it is clarified that E/C values of control rod worth at the beginning of cycle under the hot zero power condition are useful information to reduce biases and uncertainties of predicted assembly-wise power distributions during operation of hot full power. | |||||
言語 | en | |||||
内容記述タイプ | Abstract | |||||
出版者 | ||||||
言語 | en | |||||
出版者 | Taylor & Francis | |||||
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 | |||||
DOI | ||||||
関連タイプ | isVersionOf | |||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1080/00223131.2015.1126541 | |||||
ISSN | ||||||
収録物識別子タイプ | PISSN | |||||
収録物識別子 | 0022-3131 | |||||
書誌情報 |
en : Journal of Nuclear Science and Technology 巻 53, 号 10, p. 1494-1501, 発行日 2016-01-08 |
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著者版フラグ | ||||||
値 | author | |||||
URI | ||||||
識別子 | http://dx.doi.org/10.1080/00223131.2015.1126541 | |||||
識別子タイプ | DOI | |||||
URI | ||||||
識別子 | http://hdl.handle.net/2237/25271 | |||||
識別子タイプ | HDL |