None

• Material Type: 文書・図像類
• Title: None
• Author/Editor: Yukitoshi, Teruo; Yoshikawa, Kunihiko; Ueno, Kenichiro
• Author Heading: Yukitoshi, Teruo; Yoshikawa, Kunihiko; Ueno, Kenichiro
• Publication Date: 1974-02
• Publication Date (W3CDTF): 1974-02
• Alternative Title: Creep test of fuel cladding tubes for fast breeder reactor (Part III)
• Periodical title: PNC TN251 74-09
• Text Language Code: eng
• Target Audience: 一般
• Note (General): This work, which involved high temperature tensile test, internal pressure creep rupture test and examination of the ruptured test pieces, was undertaken as the third program of a series of experiment by contract with power reactor and nuclear fuel development corporation (pnc) for the purpose ofdetermining the high temperature performance of clad tubingfor the fast experimental reactor "Joyo". The materials tested under this experiment were sus 316tubes of 6.3 mm diameter and 0.35 mm thickness supplied by two different manufacturers. These materials were classified and designated for convenience sake as b-material and a-material respectively according to their manufacturers. As the result of this experiment,it was confirmed that both a and B materials demonstrated sufficient strength andelongation under 600$^{\circ}$C - 700$^{\circ}$C temperature range satisfyingthe specifications given by pnc, and that in respect of theircreep rupture strength, a-material showed a higher strengthover that of B-material while a's r; None
• Source: /PNC-TN251-74-09.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/PNC-TN251-74-09.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.: This work, which involved high temperature tensile test, internal pressure creep rupture test and examination of the ruptured test pieces, was underta...