Assessment of current understanding of mechanisms of initiation, arrest, and reinitiation of stress corrosion cracks in PWR steam generator tubing
By: prepared by S. Majumdar.
Contributors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Argonne National Laboratory.
Publisher: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 2000
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 113
Subjects: Pressurized water reactors -- Materials -- Stress corrosion.; Pressurized water reactors -- Materials -- Cracking.; Steam-boilers, Water-tube -- Materials -- Stress corrosion.; Steam-boilers, Water-tube -- Materials -- Cracking.
Notes: "Argonne National Laboratory."

Shipping list no.: 2000-0391-M.

"Date published: February 2000."

"NUREG/CR-5752."

"ANL-99/4."

Includes bibliographical references (p. 70-91).

Technical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2000] 2 microfiches : negative.

W6487.