Residual Life Assessment of Major Light Water Reactor Components
Author: Vikram N. Shah
Publisher:
Published: 1989
Total Pages: 200
ISBN-13:
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Author: Vikram N. Shah
Publisher:
Published: 1989
Total Pages: 200
ISBN-13:
DOWNLOAD EBOOKAuthor: A. S. Amar
Publisher:
Published: 1989
Total Pages: 0
ISBN-13:
DOWNLOAD EBOOKAuthor: V. N. Shah
Publisher:
Published: 1987
Total Pages: 184
ISBN-13:
DOWNLOAD EBOOKAuthor: V. N. Shah
Publisher:
Published: 1991
Total Pages:
ISBN-13:
DOWNLOAD EBOOKAuthor: Vikram N. Shah
Publisher: Elsevier Science Limited
Published: 1993
Total Pages: 943
ISBN-13: 9780444894489
DOWNLOAD EBOOKIn a comprehensive and lucid manner this book presents an understanding of the aging degradation of the major pressurized and boiling water reactor structures and components. The design and fabrication of each structure or component is briefly described followed by information on the associated stressors. Interactions between the design, materials, and various stressors that cause aging degradation are reviewed. In many cases, aging degradation problems have occurred, and the plant experience to date is analysed. The discussions summarize the available aging-related information and are supported with extensive references, including references to U.S. Nuclear Regulatory Commission (USNRC) documents, Electric Power Research Institute reports, U.S. and international conference proceedings and other publications. The book will prove a useful reference for engineers engaged in the operation and life extension of the present generation of nuclear power plants and for those engaged in the design of advanced light water reactors. It will also provide engineering students with insight into the practical materials-related issues associated with the design and operation of nuclear power plants. The work will also serve as a basis for programs to address the new aging-related issues likely to arise as plants get older.
Author: AS. Amar
Publisher:
Published: 1989
Total Pages: 13
ISBN-13:
DOWNLOAD EBOOKThe service-dependent degradation (aging) of light water reactor (LWR) pressure vessels due to irradiation embrittlement is discussed in this paper. The major variables which influence the irradiation embrittlement of LWR vessels are the copper and nickel content of the vessel materials and the fluence. The vessel beltline region is subjected to the largest fluences. A surveillance program, which consists of tension and Charpy-V-notch (CVN) testing of irradiated specimens of base, heat-affected-zone, and weld materials, is required to monitor changes in their embrittlement. Three main unresolved technical issues are: (1) the limited range and accuracy of the current correlations for calculating shifts in the reference temperature for nil-ductility transition (RTNDT) and changes in the Charpy upper shelf energy; (2) the need to demonstrate the conservatism of using CVN-based RTNDTshifts for certain sensitive reactor pressure vessel materials; and (3) the type of surveillance program required for any renewed operating license period. The damage caused by irradiation embrittlement can impact plant operating procedures, including heat up/cool down and hydrostatic test procedures, as well as the acceptability of various plant transients.
Author:
Publisher:
Published: 1994-11
Total Pages: 486
ISBN-13:
DOWNLOAD EBOOKAuthor: U.S. Nuclear Regulatory Commission. Regulatory Publications Branch
Publisher:
Published: 1990
Total Pages: 62
ISBN-13:
DOWNLOAD EBOOKAuthor: Lendell E. Steele
Publisher:
Published: 1982
Total Pages: 434
ISBN-13:
DOWNLOAD EBOOKAuthor: R. Rungta
Publisher:
Published: 1987
Total Pages: 128
ISBN-13:
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