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Materials Ageing and Degradation in Light Water Reactors
 
 

Materials Ageing and Degradation in Light Water Reactors, 1st Edition

Mechanisms and Management

 
Materials Ageing and Degradation in Light Water Reactors, 1st Edition,K L Murty,ISBN9780857092397
 
 
 

K Murty   

Woodhead Publishing

9780857092397

9780857097453

440

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Key Features

  • Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors
  • Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection
  • Chapters also focus on material management strategies

Description

Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.

Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials’ ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.

With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area.

K L Murty

K. L. Murty is a professor of nuclear engineering and materials science at North Carolina State University, USA, and a Fellow of the American Nuclear Society and the American Society for Materials International. Professor Murty has extensive experience in the field and has published over 290 technical papers on related topics. He was the first recipient of the ANS Mishima Award for outstanding research in nuclear materials.

Affiliations and Expertise

North Carolina State University, USA

Materials Ageing and Degradation in Light Water Reactors, 1st Edition

Part 1 Fundamental ageing issues and degradation mechanisms: Overview of ageing and degradation issues in light water reactors (LWRs); Corrosion in pressurized water reactors (PWRs); Creep deformation of materials in light water reactors (LWRs). Part 2 Materials ageing and degradation in particular light water reactor (LWR) components: Properties of zirconium alloys and their applications in light water reactors (LWRs); Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs); Ageing of electric cables in light water reactors (LWRs). Part 3 Materials management strategies for light water reactors (LWRs): Materials management strategies for pressurized water reactors (PWRs); Materials management strategies for VVER reactors; Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs.
 
 
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