Actions for Reactor primary coolant system pipe rupture study. Progress report No. 37, July--September 1976. [BWR].

Email RIS file
Bookmark
Report an Issue

Reactor primary coolant system pipe rupture study. Progress report No. 37, July--September 1976. [BWR].

Published
United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description
microfiche : negative ; 11 x 15 cm

Availability

I Want It
I Want It

Finding items...

Summary
The pipe rupture study is designed to extend the understanding of failure-causing mechanisms and to provide improved capability for evaluating reactor piping systems to minimize the probability of failures. This progress report summarizes the recent accomplishments of a broad program in (a) basic fatigue crack growth rate studies focused on LWR primary piping materials in a simulated BWR primary coolant environment, and (b) studies directed at quantifying weld sensitization in Type-304 stainless steel.
Report Numbers
GEAP-10207-37
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
OSTI Identifier 7215992
Research organization: General Electric Co., San Jose, CA (USA). Boiling Water Reactor Systems Dept.
View MARC record | catkey: 45372924