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• 資料種別: 文書・図像類
• タイトル: None
• 著者・編者: 太田 定雄; 石山 勇; 藤原 優行; 内田 博幸
• 著者標目: 太田 定雄; 石山 勇; 藤原 優行; 内田 博幸
• 出版年月日等: 1975-12
• 出版年（W3CDTF）: 1975-12
• 並列タイトル等: Creep test on fuel cladding tube for fast breeder reactor (Fifth program)
• タイトル（掲載誌）: PNC TN251 75-26
• 本文の言語コード: eng
• 対象利用者: 一般
• 一般注記: 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
• 一次資料へのリンクURL: /PNC-TN251-75-26.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN251-75-26.pdf
• オンライン閲覧公開範囲: 限定公開
• 連携機関・データベース: 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
• 提供元機関・データベース: 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System

• 要約等: 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...