Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water /
prepared by W.H. Cullen ; prepared for Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

APA Citation

Cullen, W. H., ENSA, I., Materials Engineering Associates., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. (1983). Fatigue crack growth rates of A 508-2 steel in pressurized, high temperature water. Washington, D.C.: The Commission.

MLA Citation

Cullen, W. H, Inc ENSA, Materials Engineering Associates, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology. Fatigue Crack Growth Rates of A 508-2 Steel In Pressurized, High Temperature Water. Washington, D.C.: The Commission, 1983.

Warning: These citations may not always be complete (especially for serials).