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Calculation of Absorbed Dose for the Overexposed Patients at the Criticality Accident in Tokai-mura
https://repo.qst.go.jp/records/43197
https://repo.qst.go.jp/records/43197f8add6ba-cc57-4d1d-bc56-90a8a34127ca
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2003-10-20 | |||||
タイトル | ||||||
タイトル | Calculation of Absorbed Dose for the Overexposed Patients at the Criticality Accident in Tokai-mura | |||||
言語 | ||||||
言語 | eng | |||||
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 | journal 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 |
Ishigure, Nobuhito
× Ishigure, Nobuhito× Endo, Akira× Yamaguchi, Yasuhiro× Kawachi, Kiyomitsu× 石榑 信人× 遠藤 章× 山口 恭弘× 河内 清光 |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The doses for the overexposed patients were estimated by the measurement result of specific activity of 24Na in blood. The present method is almost based on documents of the International Atomic Energy Agency (IAEA) and the Oak Ridge National Laboratory. The neutron energy spectrum obtained using the ANISN code (Multigroup One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering) was assumed. The values in ICRP Publication 74 were applied for the doses in each organ per unit neutron fluence. Gamma-ray dose was indirectly estimated based on (a) the result of environmental monitoring around the accident site and (b) a graph in IAEA manual, which gives the kerma ratio of neutrons and g-rays as a function of the critical volume or the atomic ratio of hydrogen to 235U. The estimated neutron doses were 5.4 Gy for patient A, 2.9 Gy for patient B and 0.81 Gy for patient C. The estimated g-ray doses were 8.5 or 13 Gy for patient A, 4.5 or 6.9 Gy for patient B, and 1.3 or 2.0 Gy for patient C. | |||||
書誌情報 |
Journal of Radiation Research 巻 42, 号 Suppl., p. S137-S148, 発行日 2001-09 |
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ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0449-3060 |