STP784

    Chapter 7—The Utility Industry and Reactor Surveillance

    Published: Jan 1983


      Format Pages Price  
    PDF (164K) 11 $25   ADD TO CART
    Complete Source PDF (3.7M) 11 $55   ADD TO CART


    Abstract

    Every commercial nuclear power reactor pressure vessel (RPV) is required to have a reactor vessel surveillance program at the time of plant licensing. The program is part of a continuing structural integrity assessment of the RPV. As such, the surveillance program supplements Section III of the American Society of Mechanical Engineers (ASME) Code [1],1 which is the design basis for nuclear power plant component pressure boundaries. The Code assumes that the materials of construction are ductile in the evaluation and design of all components. The surveillance program for each RPV is intended to provide assurance of continued applicability of the ASME Code, Appendix G, assessment of that RPV's operating limits. This assessment ensures that the RPV is always in a condition which precludes the unstable propagation of flaws in the vessel wall material.


    Author Information:

    Jenkins, RB


    Paper ID: STP29425S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP29425S


    CrossRef ASTM International is a member of CrossRef.