Degradation of Steam Generator Tubing and Components by Operation of Pressurized-water Reactors

Degradation of Steam Generator Tubing and Components by Operation of Pressurized-water Reactors
Author:
Publisher:
Total Pages:
Release: 1982
Genre:
ISBN:

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Experience in operating pressurized water reactors (PWR) has shown a number of materials degradation processes to have occurred in their steam generators. These include stress corrosion cracking (SCC), intergranular attack, generalized dissolution, and pitting attack on steam generator tubes; mechanical damage to steam generator tubes; extensive corrosion of tubing support plates (denting); and cracking of feedwater lines and steam generator vessels. The current status of the understanding of the causes of each of these phenomena is reviewed with emphasis on their possible significance to reactor safety and directions the nuclear industry and the NRC should be taking to reduce the rate of degradation of steam generator components.

Corrosion Issues in Light Water Reactors

Corrosion Issues in Light Water Reactors
Author: D Féron
Publisher: Elsevier
Total Pages: 369
Release: 2007-06-22
Genre: Technology & Engineering
ISBN: 1845693469

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Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications. The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys. With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry. Summarises key recent research on corrosion in light water reactors Includes practical case studies

Depth Profiling of Residual Stress for Shot-Peened "U"-Bend Alloy-800 Tubes for the PHWR Steam Generator

Depth Profiling of Residual Stress for Shot-Peened
Author: I. Kalpana Nayak
Publisher:
Total Pages: 14
Release: 2014
Genre: Compressive residual stress
ISBN:

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Residual tensile stresses influence the mechanical behavior in terms of fatigue and fracture resistance, stress corrosion behavior, and dimensional stability of critical components of nuclear reactors. Glass-bead shot-peened "U"-bend Alloy-800 tubes are used as steam generators in pressurized heavy water reactors (PHWRs), where stress corrosion cracking is the common cause of its premature failure. Therefore, compressive residual stresses are induced by glass-bead shot peening to overcome the tensile stresses generated more along the bend region. The variation of these compressive residual stresses as a function of depth from the surface has been estimated by successive material removal followed by stress measurement. Optimization of electropolishing parameters for removal of a fixed amount of material is carried out. Stepwise removal of material by electropolishing is proved to be better for stress analysis instead of removal "at-a-time." Effect of shot-peening pressure is also studied as a function of stress pattern developed along the depth from the surface of the straight tube and bent tube.

Nuclear Science Abstracts

Nuclear Science Abstracts
Author:
Publisher:
Total Pages: 680
Release: 1976
Genre: Nuclear energy
ISBN:

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Denting of Inconel Steam Generator Tubes in Pressurized Water Reactors. Final Report

Denting of Inconel Steam Generator Tubes in Pressurized Water Reactors. Final Report
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Publisher:
Total Pages:
Release: 1977
Genre:
ISBN:

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Denting is a form of damage that results from the rapid, linear growth of magnetite on carbon steel tube support plates in tube-to-support plate crevices. The pressure of the corrosion products distorts the tubes as well as the support plates. Although denting was first thought to be confined to those recirculating steam generators that had been converted from phosphate to AVT, it has now also been observed in plants still on phosphate, as well as in some that started on AVT. In some units, slightly abnormal eddy current signals have been observed at the top of tube sheets. No denting has been observed so far in the B and W once-through steam generators. In all, some 14 plants are affected. Inconel 600 tube defects and leaks were first observed at Surry and Turkey Point, which were severely dented. The cracks originated from the primary side, and were found to be caused by primary side stress corrosion cracking of highly strained tubing. Some minor leaks have subsequently occurred in a few other steam generators. Suggestions are included of work to elucidate the quantitative aspects of stress corrosion cracking.