Probability of pipe failure in the reactor coolant loops of Westinghouse PWR plants

• Material Type: 図書
• Title: Probability of pipe failure in the reactor coolant loops of Westinghouse PWR plants
• Author Heading: Holman, Garry S; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology; Lawrence Livermore National Laboratory
• Publication Date (W3CDTF): 1985
• Extent: microfiche
• Size: 11 × 15 cm
• Place of Publication (Country Code): US
• Text Language Code: eng
• Note (Material Type): [microform]
• Subject Heading: Pressurized water reactors; Nuclear power plants -- United States -- Pipe lines; Nuclear power plants -- United States -- Safety measures
• Note (General): "Lawrence Livermore National Laboratory."; Distributed to depository libraries in microfiche; "Date published: July 1985"--Vol. 1; "Date published: July 1985"--Vol. 4; Physical description for original version: v. : 28 cm
• Note (Bibliography): Includes bibliographies
• Note (Original Version): 原資料の出版事項: Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1985-; SUPTDOC番号: Y 3.N 88: 25/3660/v.1; テクニカルリポート番号: NUREG/CR-3660; テクニカルリポート番号: UCID-19988; GPO管理番号: 1051-H-11 (microfiche)
• Holding library: 国立国会図書館
• Call No.: YCA-Y 3.N 88:25/3660/v.1
• Data Provider (Database): 国立国会図書館 : 国立国会図書館蔵書; https://ndlsearch.ndl.go.jp
• Bibliographic ID (NDL): 000006528908; http://id.ndl.go.jp/bib/000006528908
• GPO No.: 86001786
• Bibliographic Record Category (NDL): 281

• Contents: v. 1. Summary report / G.S. Holman and C.K. Chouv. 4. Pipe failure induced by crack growth in west coast plants / D.J. Chinn ... [et al.](Provided by:...