STP761: Applications of Fatigue and Fracture Tolerant Design Concepts in the Nuclear Power Industry

    Jones, RL
    Program Manager, Program Manager, Technical Specialist, Technical Manager, and Technical Specialist, Electric Power Research Institute, Palo Alto, Calif.

    Marston, TU
    Program Manager, Program Manager, Technical Specialist, Technical Manager, and Technical Specialist, Electric Power Research Institute, Palo Alto, Calif.

    Tagart, SW
    Program Manager, Program Manager, Technical Specialist, Technical Manager, and Technical Specialist, Electric Power Research Institute, Palo Alto, Calif.

    Norris, DM
    Program Manager, Program Manager, Technical Specialist, Technical Manager, and Technical Specialist, Electric Power Research Institute, Palo Alto, Calif.

    Nickell, RE
    Program Manager, Program Manager, Technical Specialist, Technical Manager, and Technical Specialist, Electric Power Research Institute, Palo Alto, Calif.

    Pages: 19    Published: Jan 1982


    Abstract

    To assure the integrity of nuclear power plant components, fatigue and fracture tolerant design concepts have been incorporated into Sections III and XI of the ASME Code; these contain requirements for nuclear power plant design, construction, and in-service inspection. The methods used in the Code to design against fatigue and brittle fracture are described together with the fracture mechanics based procedure suggested in Section XI for the evaluation of flaws detected by in-service inspections. Some aspects of the present Code methods that could probably be improved are identified.

    Keywords:

    nuclear power reactor, design, operation, in-service inspection, flaw, fatigue, fracture, evaluation


    Paper ID: STP28853S

    Committee/Subcommittee: E08.93

    DOI: 10.1520/STP28853S


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