Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations /

Irradiation-assisted stress corrosion cracking of austenitic stainless steels and alloy 690 from Halden phase-II irradiations /

Bibliographic Details
Main Author: Chen, Y.
Corporate Authors: Argonne National Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Format: Government Document Book
Language:English
Published: [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008]
Subjects:
Boiling water reactors.
Nuclear reactors > Materials > Stress corrosion.
Nuclear reactors > Materials > Effect of radiation on.
Online Access:https://purl.fdlp.gov/GPO/LPS106255

Internet

https://purl.fdlp.gov/GPO/LPS106255

Available Online

Holdings details from Available Online
Call Number: Y 3.N 88:25/6965
 
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Y 3.N 88:25/6965 Available