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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Total Pages:
Release: 1977
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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.

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:
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Total Pages:
Release: 1982
Genre:
ISBN:

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.

EPRI Guide

EPRI Guide
Author:
Publisher:
Total Pages: 302
Release: 1983
Genre: Electric power
ISBN: