使用済燃料直接処分での処分容器の耐圧厚さの検討
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| Published in | 日本原子力学会和文論文誌 Vol. 19; no. 3; pp. 121 - 135 |
|---|---|
| Main Authors | , , , , |
| Format | Journal Article |
| Language | Japanese |
| Published |
一般社団法人 日本原子力学会
2020
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| Subjects | |
| Online Access | Get full text |
| ISSN | 1347-2879 2186-2931 |
| DOI | 10.3327/taesj.J19.007 |
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| Author | 金丸, 伸一郎 杉田, 裕 牧野, 仁史 奥村, 大成 谷口, 直樹 |
|---|---|
| Author_xml | – sequence: 1 fullname: 谷口, 直樹 organization: （国研）日本原子力研究開発機構 – sequence: 1 fullname: 杉田, 裕 organization: （国研）日本原子力研究開発機構 – sequence: 1 fullname: 金丸, 伸一郎 organization: 日揮グローバル（株） – sequence: 1 fullname: 奥村, 大成 organization: 日揮グローバル（株） – sequence: 1 fullname: 牧野, 仁史 organization: （国研）日本原子力研究開発機構 |
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| Copyright | 2020 一般社団法人 日本原子力学会 |
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| DOI | 10.3327/taesj.J19.007 |
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| EndPage | 135 |
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| References | 4) SKB, Design, Production and Initial State of the Canister, SKB Technical Report TR-10-14 (2010). 1) Japan Nuclear Cycle Development Institute, Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan, Supporting Report 2 Repository Design and Engineering Technology, JNC TN1410 2000-003 (2000). 7) The Japan Society of Mechanical Engineers, Codes for Nuclear Power Generation Facilities - Rules on Design and Construction for Nuclear Power Plants -, JSME S NC1-2007 (2007), [in Japanese]. 2) Nuclear Waste Management Organization of Japan, (Tentative title), NUMO Safety Case Report–Development of Pre-siting SDM-based Safety Case-(Draft for External Review), NUMO-TR-18-03 (2018), [in Japanese]. 5) R. Patel, C. Punshon, J. Nicholas et al., Canister Design Concepts for Disposal of Spent Fuel and High Level Waste, nagra Technical Report 12-06 (2012). 6) S. B. Ludwig, J. P. Renier, Standard and Extended Burnup PWR and BWR Reactor Models for the ORIGEN2 Computer Code, ORNL/TM-11018 (1990). 3) Japan Atomic Energy Agency, Preliminary Assessment of Geological Disposal System for Spent Fuel in Japan - First Progress Report on Direct Disposal -, JAEA-Research 2015-016 (2015), [in Japanese]. |
| References_xml | – reference: 5) R. Patel, C. Punshon, J. Nicholas et al., Canister Design Concepts for Disposal of Spent Fuel and High Level Waste, nagra Technical Report 12-06 (2012). – reference: 7) The Japan Society of Mechanical Engineers, Codes for Nuclear Power Generation Facilities - Rules on Design and Construction for Nuclear Power Plants -, JSME S NC1-2007 (2007), [in Japanese]. – reference: 3) Japan Atomic Energy Agency, Preliminary Assessment of Geological Disposal System for Spent Fuel in Japan - First Progress Report on Direct Disposal -, JAEA-Research 2015-016 (2015), [in Japanese]. – reference: 6) S. B. Ludwig, J. P. Renier, Standard and Extended Burnup PWR and BWR Reactor Models for the ORIGEN2 Computer Code, ORNL/TM-11018 (1990). – reference: 1) Japan Nuclear Cycle Development Institute, Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan, Supporting Report 2 Repository Design and Engineering Technology, JNC TN1410 2000-003 (2000). – reference: 2) Nuclear Waste Management Organization of Japan, (Tentative title), NUMO Safety Case Report–Development of Pre-siting SDM-based Safety Case-(Draft for External Review), NUMO-TR-18-03 (2018), [in Japanese]. – reference: 4) SKB, Design, Production and Initial State of the Canister, SKB Technical Report TR-10-14 (2010). |
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| SubjectTerms | design direct disposal disposal container finite element method high-level radioactive waste numerical analysis required thickness sensitivity analysis spent fuel structural analysis |
| Title | 使用済燃料直接処分での処分容器の耐圧厚さの検討 |
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