Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys
By: prepared by H.M. Chung ... [et al.]. ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Contributors: Chung, H. M.; Argonne National Laboratory.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology.
Publisher: U.S. Nuclear Regulatory Commission
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
Notes: "NUREG/CR-6687."

"ANL-00/21."

"Argonne National Laboratory."

"Date published: October 2000."

Includes bibliographical references (p. 29-31)

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