Bases for predicting the earliest penetrations due to SCC for alloy 600 on the secondary side of PWR steam generators /

Bibliographic Details
Main Author:	Staehle, R. W., 1934-2017
Corporate Authors:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, Argonne National Laboratory
Format:	Government Document Microform Book
Language:	English
Published:	Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : 2001.
Subjects:	Steam-boilers > Materials > Stress corrosion > Forecasting. Pressurized water reactors > Materials > Stress corrosion > Forecasting. Nuclear power plants > Piping > Materials > Stress corrosion > Forecasting.