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Author: Vikram N. Shah Publisher: Elsevier Science Limited ISBN: 9780444894489 Category : Technology & Engineering Languages : en Pages : 943
Book Description
In 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: Vikram N. Shah Publisher: Elsevier Science Limited ISBN: 9780444894489 Category : Technology & Engineering Languages : en Pages : 943
Book Description
In 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: Robert Odette Publisher: Newnes ISBN: 012397349X Category : Technology & Engineering Languages : en Pages : 676
Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Author: Russell H. Jones Publisher: ASM International(OH) ISBN: Category : Science Languages : en Pages : 466
Book Description
Details the many conditions under which stress-corrosion cracking (SCC) can occur, the parameters which control SCC, and the methodologies for mitigating and testing for SCC, plus information on mechanisms of SCC with experimental data on a variety of materials. Contains information about environmen
Author: Publisher: Elsevier ISBN: 0081028660 Category : Science Languages : en Pages : 4871
Book Description
Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Author: Steve Bruemmer Publisher: John Wiley & Sons ISBN: 1118787773 Category : Technology & Engineering Languages : en Pages : 1776
Book Description
This collection presents an exchange of ideas among scientists and engineers about the economic and safety concerns surrounding environmentally induced materials problems which lead to nuclear power plant outages. Scientists and engineers concerned with the environmental degradation processes (corrosion, mechanical, and radiation effects) present their latest results on such topics as life extension/relicensing and materials problems associated with spent fuel storage and radioactive waste disposal. This collection will be of interest to utility engineers, reactor vendor engineers, plant architect engineers, researchers concerned with materials degradation, and consultants involved in design, construction, and operation of water reactors.
Author: Vikram N. Shah
Author: Vikram N. Shah
Author: OECD Nuclear Energy Agency
Author: U.S. Nuclear Regulatory Commission
Author: Robert Odette
Author: J. Sinnappan
Author: Russell H. Jones
Author: 
Author: 
Author: Steve Bruemmer
Author: Charles P. Sturrock