Bases for predicting the earliest penetrations due to SCC for alloy 600 on the secondary side of PWR steam generators
By: prepared by Roger W. Staehle.
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: 2001
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 104
Subjects: Steam-boilers -- Materials -- Stress corrosion -- Forecasting.; Pressurized water reactors -- Materials -- Stress corrosion -- Forecasting.; Nuclear power plants -- Piping -- Materials -- Stress corrosion -- Forecasting.
Notes: "Under contract to Argonne National Laboratory."

Shipping list no.: 2002-0038-M.

"September 2001."

"NUREG/CR-6737."

"ANL-01/20."

"RWS 151."

Includes bibliographical references (p. 93-104).

Technical: Topical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2001] 2 microfiches : negative.

W6487.