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

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Abstract
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.

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