ナトリウム冷却高速炉金属燃料の過出力時における燃料温度解析

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Author: 水野朋保ほか

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Publication date: 2013-06

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Note (General)：: Metallic fuel, U-Pu(TRU)-Zr is a fuel candidate for Sodium-cooled fast reactor (SFR) selected as a possible promising future nuclear reactor system in...

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Summary, etc.：: Metallic fuel, U-Pu(TRU)-Zr is a fuel candidate for Sodium-cooled fast reactor (SFR) selected as a possible promising future nuclear reactor system in...

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Material Type: 文書・図像類
Title: ナトリウム冷却高速炉金属燃料の過出力時における燃料温度解析
Author/Editor: 水野朋保
小山真一
皆藤威二
上羽智之
田中健哉
Author Heading: 水野朋保
小山真一
皆藤威二
上羽智之
田中健哉
Publication Date: 2013-06
Publication Date (W3CDTF): 2013-06
Alternative Title: Fuel temperature analyses at overpower of metallic fuel pin for sodium-cooled fast reactors
Periodical title: JAEA-Technology 2013-009
Text Language Code: eng
Target Audience: 一般
Note (General): Metallic fuel, U-Pu(TRU)-Zr is a fuel candidate for Sodium-cooled fast reactor (SFR) selected as a possible promising future nuclear reactor system in Generation-IV international forum (GIF). Design studies were performed in the Japanese feasibility study on commercialized fast reactor cycle system, and the irradiation behavior of metallic fuel is under investigation through analytical fuel performance code calculations with preliminary analytical models. As fuel temperature analyses at overpower events are also major interest, some calculations of U-Pu(TRU)-Zr fuel irradiation performance were conducted by a simplified calculation program developed in JAEA. The calculated fuel temperature at the maximum power of overpower events, 110-120\% of steady state power, was around 1100K in maxim. It is clear that this temperature was low enough to avoid fuel melting in the event.
U-Pu(TRU)-Zrを成分とする金属燃料は、第4世代原子力システム国際フォーラム(GIF)において有望な原子炉として選定されたナトリウム冷却炉(SFR)の候補燃料である。金属燃料の設計研究は日本における高速炉の実用化研究で実施され、照射挙動に関して挙動解析コードを用いた予備評価を実施中である。過出力事象時の温度解析は燃料健全性評価上重要であるため、U-Pu(TRU)-Zr燃料の照射挙動評価を原子力機構で開発した簡易計算プログラムを用いて実施した。過出力事象時の最大出力、すなわち定常運転時の110-120\%の出力条件において、燃料温度は最高で1100Kと評価され、燃料溶融が回避できることが示された。
Source: /JAEA-Technology-2013-009.pdf （fulltext）
https://jopss.jaea.go.jp/pdfdata/JAEA-Technology-2013-009.pdf
Access Restrictions: 限定公開
Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）
https://irdb.nii.ac.jp
Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System