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ASM Failure Analysis Case Histories

Handbook of Case Histories in Failure Analysis

Edited by
Khlefa A. Esaklul
Khlefa A. Esaklul
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ASM International
Volume
1
ISBN electronic:
978-1-62708-214-3
Publication date:
1992
Book Chapter

Corrosion Fatigue Cracking of a Steam Generator Vessel From a Pressurized Water Reactor

By
Carl J. Czajkowski
Carl J. Czajkowski
Department of Nuclear Energy Brookhaven National Laboratory
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Published:
1992
Page range:
136 - 139

Abstract

A pair of steam generators operating at a pressurized water reactor site were found to be leaking near a closure weld. The generators were the vertical U-tube type, constructed from ASTM A302 grade B steel. The shell material exhibited high hardness values prior to confirmatory heat treatment, indicating high residual stresses in the area of the weld. All cracks were transgranular and were associated with pits on the inside surfaces of the vessels. It was concluded that the cracking was caused by a low-cycle corrosion fatigue phenomenon, with cracks initiating at areas of localized corrosion and propagating by fatigue. The cause of the pitting/cracking was related to the unit's copper species in solution.

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Carl J. Czajkowski, 1992. "Corrosion Fatigue Cracking of a Steam Generator Vessel From a Pressurized Water Reactor", Handbook of Case Histories in Failure Analysis, Khlefa A. Esaklul

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