Published 1994 | Version v1
Book

Failure investigation of type 410 stainless steel retaining block studs of swing check valves in pressurized water reactors

Creators

  • 1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Nuclear Energy Systems

Description

Retaining block studs in swing check valves employed in Emergency Core Cooling System of pressurized water reactors have been the subject of cracking during the past few years. The studs are made from ASTM A-193 Gr. 6 type 410 stainless steel material. USNRC issued an information notice on the issue encouraging utilities to take appropriate actions to monitor/replace the studs so as to prevent a potential dislodging of the valve retaining blocks that can cause flow blockage in the valves. The current paper summarizes the results of a metallurgical investigation aimed at establishing the mechanism and cause(s) of the valve stud cracking. Potential candidate replacement materials to remedy the cracking issue are also considered

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineering.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1355-X
Imprint Title
Pressure vessels, pumps, valves, pipe supports and components. PVP-Volume 282
Imprint Pagination
162 p.
Journal Page Range
p. 95-102.

Conference

Title
1994 pressure vessels and piping conference.
Dates
19-23 Jun 1994.
Place
Minneapolis, MN (United States).

Optional Information

Secondary number(s)
CONF-940613--.