Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water
By: W.H. Cullen, Jr. ... [et al.] ; prepared for U.S. Nuclear Regulatory Commission
Contributors: Cullen, W. H; Naval Research Laboratory (U.S.). Thermostructural Materials Branch; U.S. Nuclear Regulatory Commission
Series: NRL memorandum report -- 4063
Publisher: Naval Research Laboratory; Available from U.S. Nuclear Regulatory Commission
Published: 1979
Place of publication: Washington, D.C
Language: eng
Number of pages: 53
Subjects: Nuclear pressure vessels; Steel, Effect of radiation on; Steel -- Brittleness; Steel -- Fatigue; Steel -- Stress corrosion
Notes: Cover title

"Thermostructural Materials Branch, Material Science and Technology Division."

"September 28, 1979."

"NUREG/CR 0969."

Includes bibliographical references