Actions for Intergranular stress corrosion cracking of sensitized stainless steels. Final report

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Intergranular stress corrosion cracking of sensitized stainless steels. Final report

Author
Vyas, B.
Published
United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Isaacs, H. S. and Weeks, J. R.

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Summary
A study was conducted of the intergranular stress corrosion cracking of materials used in Boiling Water Reactors (BWR) aimed at developing an understanding of the mechanism(s) of this mode of failure and at developing tests to determine the susceptibility of a given material to this form of attack.
Report Numbers
BNL-NUREG-50596
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: EY-76-C-01-0016
OSTI Identifier 7113075
Research organization: Brookhaven National Lab., Upton, NY (USA).
View MARC record | catkey: 42515932