Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

[+] Author and Article Information
Charles Z. Serpan

U. S. Naval Research Laboratory (NRL), Metallurgy Division (Code 6390), Washington, D. C.

L. E. Steele

Reactor Materials Branch, U. S. Naval Research Laboratory (NRL), (Code 6390), Metallurgy Division, Washington, D. C.

J. R. Hawthorne

Mechanical Metallurgy Section, U. S. Naval Research Laboratory (NRL), Metallurgy Division, (Code 6390), Washington, D. C.

J. Basic Eng 89(1), 221-232 (Mar 01, 1967) (12 pages) doi:10.1115/1.3609556 History: Received October 20, 1965; Online November 03, 2011


The meaning and purpose of reactor pressure vessel surveillance is briefly discussed. Features of the surveillance programs in the Yankee, Big Rock Point, SM-1, and SM-1A reactors are briefly described along with results of testing metallurgical specimens from these programs. Additionally, the surveillance program to be effected in the Army MH-1A reactor is described. Certain problems which have occurred in the course of these programs are discussed as well as the proposed ASTM recommendations for radiation-damage surveillance programs. The value of these programs to reactor operators is reviewed with relation to the results obtained to date.

Copyright © 1967 by ASME
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