Environmentally assisted cracking in light water reactors Semiannual report, April--September 1987 Volume 5.

Environmentally assisted cracking in light water reactors [electronic resource] : Semiannual report, April--September 1987 Volume 5.

This report summarizes work performed by Argonne National Laboratory on environmentally assisted cracking in light water reactors during the six months from April to September 1987. The stress corrosion cracking (SCC) behavior of Types 304, 316NG, and 347 stainless steel (SS) was investigated by mea...

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Online Access: Full Text (via OSTI)
Corporate Authors: U.S. Nuclear Regulatory Commission (Researcher), Argonne National Laboratory (Researcher), Historical Energy Database (United States)
Format: Government Document Electronic eBook
Language:English
Published: Rockville, Md. : Oak Ridge, Tenn. : U.S. Nuclear Regulatory Commission ; Distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1989.
Subjects:
21 specific nuclear reactors and associated plants
36 materials science
Bwr type reactors
Fracture mechanics
Pwr type reactors
Stainless steel304
Stainless steel316
Stainless steel347
Copper
Crack propagation
Et al
Specific nuclear reactors and associated plants
Materials science
Stainless steel-304
Stainless steel-316
Stainless steel-347

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Call Number: E 1.99:ANL-88-32-Vol.5
E 1.99:ANL-88-32-Vol.5 Available

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