Preliminary analysis of the effect of fatigue loading and crack propagation on crack acceptance criteria for nuclear power plant components
By: W.F. Anderson, G.H. Weidenhamer, E.C. Johns
Contributors: Weidenhamer, G. H; Johns, E. C.; U.S. Nuclear Regulatory Commission. Division of Engineering Standards
Publisher: Division of Engineering Standards, Office of Standards Development, U.S. Nuclear Regulatory Commission; Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission; National Technical Information Service
Published: 1981
Place of publication: Washington, D.C; Springfield, Va
Language: eng
Subjects: Principal components analysis; Nuclear reactors -- Maintenance and repair; Nuclear reactors -- Materials; Materials -- Fatigue
Notes: "Date published: April 1981."

"NUREG-0726."

Includes bibliographical references