Published 1989 | Version v1
Book

Leak-before-break analysis of type 304 stainless steel piping

  • 1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA)
  • 2. General Electric Co., Pleasanton, CA (USA)

Description

The nuclear materials production reactors at the Savannah River Plant (SRP) were designed and built in the 1950's and have operated successfully since that time. Unlike commercial power reactors, the production reactors are moderated and cooled by heavy water and are operated at moderately low temperatures and internal pressures. In addition, the entire primary coolant pressure boundary is constructed of Type 304 stainless steel or its cast equivalent, CF-8, except for seals, gaskets and other serviceable parts. This paper presents the leak-before-break demonstration of the SRP primary coolant piping

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
375 p.
Series
Volume G. Fracture mechanics and non-destructive evaluation.
Journal Page Range
p. 369-374.

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--.