Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components

Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components [microform] / prepared by O.K. Chopra, W.J. Shack ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

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Bibliographic Details
Main Author: Chopra, O. K.
Corporate Authors: Argonne National Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors: Shack, W. J.
Format: Government Document Microfilm Book
Language:English
Published: Washington, D.C. : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, [1995]
Subjects:
Nuclear reactors > Equipment and supplies > Maintainability.
Stainless steel > Embrittlement.
Stainless steel > Fracture.

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