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• Material Type: 文書・図像類
• Title: None
• Author/Editor: 太田 定雄; 石山 勇; 藤原 優行; 内田 博幸
• Author Heading: 太田 定雄; 石山 勇; 藤原 優行; 内田 博幸
• Publication Date: 1975-12
• Publication Date (W3CDTF): 1975-12
• Alternative Title: Creep test on fuel cladding tube for fast breeder reactor (Fifth program)
• Periodical title: PNC TN251 75-26
• Text Language Code: eng
• Target Audience: 一般
• Note (General): Elevated temperature tensile tests and uniaxial creep tests at 700 c, and internal pressure creep rupture tests at 650 c and 750 c were performed on the fuel cladding tubes to be used in the core of the Japan prototype fast breeder reactor "MONJU" and the second core of the Japan experimental fast breeder reactor "JOYO". Three kinds of fuel cladding tubes a, b, and c, made by two manufactures, were tested. Tubes b and c have larger grain size than tube a and tube c had rather higher nitrogen content than tubes a and b. Results are summarized as follows: 1) The tensile properties of tubes a, b, and c were almost equivalentand satisfied the specification given by PNC. 2) Creep strength of tube b was higher than that of tube a. 3) Tube b showed longer creep rupture lives than tube a in the range of internal pressures applied at either test temperature. Creep rupture strength of tube c was equivalent to that of tube b at 750 c. 4) There were significant differences between the creep and creep rupture; None
• Source: /PNC-TN251-75-26.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN251-75-26.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

• Summary, etc.: Elevated temperature tensile tests and uniaxial creep tests at 700 c, and internal pressure creep rupture tests at 650 c and 750 c were performed on t...