Potential for low fracture toughness and lamellar tearing in PWR steam generator and reactor coolant pump supports
Subtitle: unresolved safety issue A-12
Publisher: Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
Published: 1983
Place of publication: Washington, D.C
Language: eng
Subjects: Pressurized water reactors; Nuclear reactors -- United States -- Materials -- Testing
Notes: Supersedes NUREG-0577, for comment, October 1979

Distributed to depository libraries in microfiche

"Date published: October 1983."

"NUREG-0577, rev.1."

Includes bibliographical references

Technical report