Published 1989 | Version v1
Book

Indirect failure probability of Type 304 stainless steel piping

  • 1. RPK Structural Mechanics Consulting, Yorba Linda, CA (USA)
  • 2. Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA)
  • 3. Impell Corp., Mission Viejo, CA (USA)

Description

The NRC has developed criteria for establishing leak-before-break conditions in high energy piping. The Savannah River Plant production reactors operate at relatively low temperature and pressure, making them moderate energy systems. While these reactors are not under NRC jurisdiction, the NRC criteria of NUREG-1061 provide a useful and complete framework for demonstrating leak-before-break (LBB). These criteria include demonstrating a low failure probability of piping form indirect cause (resulting from the failure of surrounding equipment and structures). This paper presents an evaluation of the seismic indirect failure probability for the primary coolant piping at Savannah River Plant

Additional details

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structural mechanics in reactor technology
Imprint Pagination
967 p.
Series
Seismic response analysis and design.
Journal Page Range
p. 929-934.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

Optional Information

Secondary number(s)
CONF-890855--.