Mechanical properties of thermally aged cast stainless steels from Shippingport Reactor components
By: prepared by O.K. Chopra, W.J. Shack ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Contributors: Shack, W. J.; Argonne National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
Publisher: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1995
Place of publication: Washington, D.C
Language: eng
Format: Microform
Number of pages: 154
Subjects: Nuclear reactors -- Equipment and supplies -- Maintainability; Steel, Stainless -- Embrittlement; Steel, Stainless -- Fracture
Notes: "Performing organization: Argonne National Laboratory." -- Bibliographic data sheet.

"Date published: April 1995."

"NUREG/CR-6275."

"ANL-94/37."

"NRC Job Code A2256."

Includes bibliographical references (p. 51-53).

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [1995]. 2 microfiches : negative.