Inclusion of unstable ductile tearing and extrapolated crack-arrest toughness data in PWR vessel integrity assessment
By: prepared by T.L. Dickson, R.D. Cheverton, and D.K. Shum.
Contributors: Cheverton, R. D.; Shum, D. K. M.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; Oak Ridge National Laboratory.
Publisher: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1990
Place of publication: Washington, DC
Language: eng
Number of pages: 25
Subjects: Nuclear pressure vessels -- Reliability -- Mathematical models.; Pressurized water reactors -- Reliability -- Mathematical models.; Fracture mechanics.; Steel -- Fracture.; Steel -- Ductility.
Notes: "Oak Ridge National Laboratory."

Distributed to depository libraries in microfiche.

No longer available for sale by the Supt. of Docs.

"Date published: May 1990."

"NUREG/CR-5473."

"ORNL/TM-11450."

Includes bibliographical references (p. 22-24).

Technical.

B0119.