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Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems /

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Bibliographic Details
Main Author: Chopra, O. K. (Author)
Corporate Authors: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering (sponsoring body.), Argonne National Laboratory
Format: Government Document eBook
Language:English
Published: Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2016.
Edition:Revision 2.
Subjects:
Stainless steel > Effect of temperature on.
Stainless steel > Embrittlement.
Light water reactors > Materials > Effect of temperature on.
Light water reactors > Materials > Embrittlement.
Online Access:https://purl.fdlp.gov/GPO/gpo76398

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https://purl.fdlp.gov/GPO/gpo76398

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Call Number: Y 3.N 88:25/4513/REV.2
 
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