Skip to Main Content
ASM Failure Analysis Case Histories

Handbook of Case Histories in Failure Analysis

Edited by
Khlefa A. Esaklul
Khlefa A. Esaklul
Search for other works by this author on:
ASM International
Volume
1
ISBN electronic:
978-1-62708-214-3
Publication date:
1992
Book Chapter

Failure Analysis of the Moderator Branch Pipe of a Pressurized Hot Water Reactor

By
Antonio Florio
Antonio Florio
Gerencia de Desarrollo, Comisión Nacional de Energía Atómica
Search for other works by this author on:
;
Juan C. Crespi
Juan C. Crespi
Gerencia de Desarrollo, Comisión Nacional de Energía Atómica
Search for other works by this author on:
Published:
1992
Page range:
153 - 156

Abstract

Type 347 stainless steel moderator circuit branch piping in a pressurized hot water reactor was experiencing frequent leakage. Investigation of the problem involved failure analysis of leaking pipe specimens, analytical stress analysis, and determination of “leak-before-break” conditions using fracture mechanics and thermal fatigue simulation tests. Failure analysis indicated that cracking had been initiated by thermal fatigue. Data from the analysis were used in making the leak-before-break predictions. It was determined that the cracks could grow to two-thirds of the circumferential length of the pipe without catastrophic failure. A thin stainless steel sleeve was inserted in the branch pipe to resolve the problem.

You do not currently have access to this content.
Don't already have an account? Register

Antonio Florio, Juan C. Crespi, 1992. "Failure Analysis of the Moderator Branch Pipe of a Pressurized Hot Water Reactor", Handbook of Case Histories in Failure Analysis, Khlefa A. Esaklul

Download citation file:


Close
Close Modal
This Feature Is Available To Subscribers Only

Sign In or Create an Account

Close Modal
Close Modal