Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys
By: prepared by H.M. Chung ... [et al.].
Contributors: Chung, H. M.; Argonne National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
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: 2000
Place of publication: Washington, DC
Language: eng
Format: Microform
Number of pages: 31
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 steel alloys.
Notes: "Argonne National Laboratory."

Shipping list no.: 2001-0110-M.

"Date published: October 2000."

"NUREG/CR-6687."

"ANL-00/21."

Includes bibliographical references (p. 29-31).

Technical; topical.

Microfiche. [Washington, D.C.] : Supt. of Docs., U.S. G.P.O., [2000] 1 microfiche : negative.

W6610.