Evaluation of cracking in feedwater piping adjacent to the steam generators in nine pressurized water reactor plants
By: prepared by Alfred Goldberg, Ronald D. Streit, and Robert D. Scott ; prepared for Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
Contributors: Streit, Ronald D; Scott, Robert G; U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation; Lawrence Livermore National Laboratory
Publisher: The Office; Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; National Technical Information Service
Published: 1980
Place of publication: Washington, D. C; Springfield, Va
Language: eng
Number of pages: 190
Subjects: Pipe, Steel; Steel -- Fractures; Steam-boilers; Pressurized water reactors
Notes: "Lawrence Livermore Laboratory."

"Date published: October 1980."

"NRC FIN no. A0225."

"NUREG/CR-1603."

"UCL-53000."

Includes bibliographical references