Irradiation-assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor
By: prepared by H.M. Chung, W.R. Ruther, R.V. Strain.
Contributors: Ruther, W. R.; Strain, R. V.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.; Argonne National Laboratory.
Publisher: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission; Supt. of Docs., U.S. G.P.O. [distributor]
Published: 1999
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 30
Subjects: Boiling water reactors.; Nuclear reactors -- Materials -- Stress corrosion.; Nuclear reactors -- Materials -- Effect of radiation on.
Other titles: Irradiation assisted stress corrosion cracking of model austenitic stainless steels irradiated in the Halden reactor.
Notes: "Argonne National Laboratory."

Shipping list no.: 99-0533-M.

"Date published: March 1999."

Includes bibliographical references (p. 29-30).

Technical; topical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [1999] 1 microfiche : negative.

W6610.