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中性子・光子モンテカルロ計算コードMCNPによる核融合炉遮蔽計算
https://repo.qst.go.jp/records/58758
https://repo.qst.go.jp/records/5875838cf9c4a-0b43-45c6-ae90-b57ed6cdc5fb
Item type | 一般雑誌記事 / Article(1) | |||||
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公開日 | 2017-06-09 | |||||
タイトル | ||||||
タイトル | 中性子・光子モンテカルロ計算コードMCNPによる核融合炉遮蔽計算 | |||||
言語 | ||||||
言語 | jpn | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
佐藤, 聡
× 佐藤, 聡× 佐藤 聡 |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | In the shielding calculation of the nuclear fusion reactor, neutron and photon transport calculations have been performed by using three dimensional Monte Carlo calculation code MCNP. Recent applications with MCNP are reported in the shielding calculations of the nuclear fusion reactor. CAD/MCNP conversion codes have been developed, and MCNP calculation geometry data are automatically created by CAD/MCNP conversion codes. Details and application results are reported on the CAD/MCNP conversion code. By modifying the MCNP code and nuclear data library, the effective dose rates after reactor shutdown have been calculated with high accuracy. The calculation method and the application results are reported on the effective dose rates after shutdown. | |||||
書誌情報 |
応用物理学会放射線分科会会誌「放射線」 巻 43, 号 2, p. 73-80, 発行日 2017-05 |
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出版者 | ||||||
出版者 | 応用物理学会放射線分科会 | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0285-3604 |