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• Material Type: 規格・テクニカルリポート類
• Title: None
• Author/Editor: 山中 諒治; 梶山 登司; 阪西 健一
• Publication Date: 1984-11
• Publication Date (W3CDTF): 1984
• Alternative Title: Post Irradiation Examination of Fugen MOX Fuel
• Periodical title: PNC TN341 84-18
• Target Audience: 一般
• Note (General): 出版タイプ： NA; The Power Reactor and Nuclear Fuel Development Corporation (PNC) has obtained good performance of MOX fuel in the Fugen. The Fugen is a 165MWe prototype heavy water moderated, boiling light water cooled reactor using mainly MOX fuel fabricated in Tokai Woreks PNC. Since the start-up test in 1978, 284MOX and 284UO2 fuel assemblies in total were loaded into the core, and 156MOX and 192UO2 ones discharged. The maximum burnup of discharged fuel assemblies reached about 14,000MWd/t and no fuels have failed. The post irradiat ion examination (PIE) of MOX fuel discharged from the Fugen was started in 1983 to clarify the behavior of MOXf uels. This report mainly presents results of non-destructive tests in the above PIE of MOX fuel, which has been irradiated to 13,600MWd/t of burnup and stayed in the core about 4 years. Important items to evaluate the performance of MOX fuel are mainly cladding deformation and fission gas release. Prior to PIE, the fuel assembly was treated by anultrasonic washing in order to investigate the state of crudadhering to fuel surface. The fuel rod surface was covered thickly with crud was easily removed by this treatment. Cladding deformation; None
• Source: /PNC-TN341-84-18.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN341-84-18.pdf
• Access Restrictions: インターネット公開
• 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

• Summary, etc.: The Power Reactor and Nuclear Fuel Development Corporation (PNC) has obtained good performance of MOX fuel in the Fugen. The Fugen is a 165MWe prototy...