Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion


Book Description

This paper provides historical context and future direction on selected contributions to understanding zirconium-alloy deformation and corrosion in light water reactors. More detailed discussion of the relative importance of electrochemical potential and hydrogen pickup on nodular corrosion is provided. Since nodular corrosion was observed about 50 years ago, several explanations have been proposed. None have explained all the observations, especially the sharp transition between nodular-free and nodular-covered regions of some fuel rods, with the transition being reversed between high- and low-power regions. However, the effect of electrochemical potential dominates any effects of hydrogen, other than the effect of hydrogen on electrochemical potential.




Zirconium in the Nuclear Industry


Book Description

The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr




Zirconium Alloy Performance in Light Water Reactors


Book Description

Various aspects of zirconium alloy development for light water reactors in the UK and Scandinavia are reviewed, including the contribution made by some unique nuclear testing facilities. Among the problems encountered were the irradiation enhancement of corrosion and hydrogen pickup, crud deposition, iodine-induced stress-corrosion cracking on power ramping, and severe cladding deformation in loss-of-coolant accident conditions. The causes and behavior of defects, including hydride defects and fretting corrosion, are discussed.




Zirconium Alloy Performance in Light Water Reactors


Book Description

Various aspects of zirconium alloy development for light water reactors in the UK and Scandinavia are reviewed, including the contribution made by some unique nuclear testing facilities. Among the problems encountered were the irradiation enhancement of corrosion and hydrogen pickup, crud deposition, iodine-induced stress-corrosion cracking on power ramping, and severe cladding deformation in loss-of-coolant accident conditions. The causes and behavior of defect, including hydride defects and fretting corrosion, are discussed. The original paper was published by ASTM International in STP 1245, Zirconium in the Nuclear Industry: Tenth International Symposium, 1994, pp. 1932.







Materials Ageing and Degradation in Light Water Reactors


Book 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. - 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







Zirconium in the Nuclear Industry


Book Description




Zirconium in the Nuclear Industry


Book Description




Zirconium in the Nuclear Industry


Book Description