Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports".

Bibliographic Details
Format:	Government Document eBook
Language:	English
Published:	[Washington, D.C ] : [U.S. Nuclear Regulatory Commission], 1980.
Series:	Generic letter ; 80-47.
Subjects:	Pressurized water reactors. Nuclear reactors > Materials > Testing.
Online Access:	https://purl.fdlp.gov/GPO/gpo153905

Available Online