| アイテムタイプ |
itemtype_ver1(1) |
| 公開日 |
2025-07-07 |
| タイトル |
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|
タイトル |
Reduced order SP3 core calculation based on local/global iterations using proper orthogonal decomposition |
|
言語 |
en |
| 著者 |
Ito, Masato
Endo, Tomohiro
Yamamoto, Akio
Takeishi, Taichi
Kodama, Yasuhiro
Hyoudou, Hideaki
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| アクセス権 |
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|
アクセス権 |
open access |
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アクセス権URI |
http://purl.org/coar/access_right/c_abf2 |
| 権利 |
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|
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 12/12/2024, available at: https://doi.org/10.1080/00223131.2024.2436958 |
|
言語 |
en |
| 内容記述 |
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内容記述タイプ |
Abstract |
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内容記述 |
For an efficient heterogeneous neutron transport calculation, this study newly proposes a reduced order core calculation method by applying proper orthogonal decomposition (POD) to the simplified P3 (SP3) calculation with the local/global iterations. The fine mesh SP3 calculation (local calculation) for each single assembly can be efficiently solved using POD, thanks to the matrix form-based SP3 equation and the relatively small system of linear equations. By reconstructing the fine mesh distribution of neutron flux and partial neutron currents from the POD bases and the expansion coefficients estimated by the local calculation, the partial current-based coarse mesh finite difference (p-CMFD) calculation is applied to the coarse mesh calculation (global calculation). Using the global calculation results, each local boundary condition can be updated. These local and global calculations are iterated until convergence. Through a two-dimensional UO2-MOX whole core calculation with different fuel loading patterns, the proposed method is verified in comparison with the reference result by the conventional fine mesh SP3 calculation. The calculation results show that the proposed method accurately reconstructs the fine mesh distribution of neutron flux. |
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言語 |
en |
| 内容記述 |
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内容記述タイプ |
Other |
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内容記述 |
Published online: 12 Dec 2024 |
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言語 |
en |
| 出版者 |
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出版者 |
Taylor & Francis |
|
言語 |
en |
| 言語 |
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|
言語 |
eng |
| 資源タイプ |
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資源タイプresource |
http://purl.org/coar/resource_type/c_6501 |
|
タイプ |
journal article |
| 出版タイプ |
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|
出版タイプ |
AM |
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出版タイプResource |
http://purl.org/coar/version/c_ab4af688f83e57aa |
| 関連情報 |
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関連タイプ |
isVersionOf |
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|
識別子タイプ |
DOI |
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|
関連識別子 |
https://doi.org/10.1080/00223131.2024.2436958 |
| 収録物識別子 |
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収録物識別子タイプ |
PISSN |
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収録物識別子 |
0022-3131 |
| 書誌情報 |
en : Journal of Nuclear Science and Technology
巻 62,
号 4,
p. 366-378,
発行日 2025
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| ファイル公開日 |
|
|
日付 |
2025-12-12 |
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日付タイプ |
Available |
JNST62_4_pp366-378_2025.pdf (2.1 MB)
