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Boiling water reactors > Materials > Stress corrosion
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Stress corrosion

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1.
Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments
Published
[Washington, DC] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Online
http://purl.access.gpo.gov/GPO/LPS126328
Location
Yale Internet Resource >> None
Format
Books / Online
2.
Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internals
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/6677
Format
Books / Microforms
3.
Residual stresses and associated stress intensity factors in core shroud weldments
Published
Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1999.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:25/5675
Format
Books / Microforms
4.
Status report intergranular stress corrosion cracking of BWR core shrouds and other internal components
Published
Washington, DC : Division of Engineering, 0ffice of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Supt. of Docs., U.S. G.P.O. [distributor], 1996.
Location
SML, Microform (Non-Circulating) >> Y 3.N 88:10/1544
Format
Books / Microforms