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  1. B200 工学部/工学研究科
  2. B200a 雑誌掲載論文
  3. 学術雑誌

Bias factor method using random sampling technique

http://hdl.handle.net/2237/25271
http://hdl.handle.net/2237/25271
4caaf36b-409c-4a49-b46c-110dc21c98f8
名前 / ファイル ライセンス アクション
JNST53_10_pp1494-1501_2016.pdf JNST53_10_pp1494-1501_2016.pdf ファイル公開:2017/01/08 (782.5 kB)
Item type 学術雑誌論文 / Journal Article(1)
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

WEKO 68393

en Endo, Tomohiro

Search repository
Yamamoto, Akio

× Yamamoto, Akio

WEKO 68394

en Yamamoto, Akio

Search repository
Watanabe, Tomoaki

× Watanabe, Tomoaki

WEKO 68395

en Watanabe, Tomoaki

Search repository
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
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
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