Fatigue damage in major light water reactor components

Title: Fatigue damage in major light water reactor components

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Abstract

The US Nuclear Regulatory Commission (NRC) is sponsoring a Nuclear Plant Aging Research (NPAR) program for resolution of technical safety issues associated with aging of, and license renewal for, commercial nuclear power plants. One project in the NPAR program is to develop the appropriate technical procedures and criteria for the NRC to assess the residual life of the major light water reactor components and structures. These assessments will help the NRC resolve certain safety issues and develop policies and guidelines for marking timely license-renewal decisions. Most of the effort for this residual life assessment project is focused on integrating, evaluating, and updating the technical information relevant to aging and license renewal from current and completed NRC and industry research programs. The major components for this project were selected according to the role they play in containing any fission products that may be released during an accident. The selected components include primary pressure boundary components, primary containments, cables and connectors, emergency diesel generators, and reactor pressure vessel supports. The degradation sites, mechanisms, stressors, and potential failure modes for these major components have been identified and evaluated. The results show that fatigue is a major degradation mechanism acting at several critical locations.more »« less

Authors:: Shah, V N; Server, W L

Publication Date:: 1987-01-01

OSTI Identifier:: 7148345

Report Number(s):: CONF-8711195-
Journal ID: CODEN: TANSA; TRN: 88-028656

Resource Type:: Conference

Journal Name:: Trans. Am. Nucl. Soc.; (United States)

Additional Journal Information:: Journal Volume: 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR COMPONENTS; PWR TYPE REACTORS; FATIGUE; AGING; CORROSION; CRACK PROPAGATION; MICROSTRUCTURE; NOZZLES; PRESSURE VESSELS; REACTOR LICENSING; REACTOR OPERATION; RESEARCH PROGRAMS; RESIDUAL STRESSES; SERVICE LIFE; STEAM GENERATORS; WELDED JOINTS; BOILERS; CHEMICAL REACTIONS; CONTAINERS; CRYSTAL STRUCTURE; JOINTS; LICENSING; MECHANICAL PROPERTIES; OPERATION; REACTORS; STRESSES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

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                    Shah, V N, and Server, W L. Fatigue damage in major light water reactor components.  United States: N. p., 1987. 
        Web.

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                    Shah, V N, & Server, W L. Fatigue damage in major light water reactor components.  United States.

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                    Shah, V N, and Server, W L. Thu .  
        "Fatigue damage in major light water reactor components".  United States.

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@article{osti_7148345,

  title        = {Fatigue damage in major light water reactor components},

  author       = {Shah, V N and Server, W L},

  abstractNote = {The US Nuclear Regulatory Commission (NRC) is sponsoring a Nuclear Plant Aging Research (NPAR) program for resolution of technical safety issues associated with aging of, and license renewal for, commercial nuclear power plants. One project in the NPAR program is to develop the appropriate technical procedures and criteria for the NRC to assess the residual life of the major light water reactor components and structures. These assessments will help the NRC resolve certain safety issues and develop policies and guidelines for marking timely license-renewal decisions. Most of the effort for this residual life assessment project is focused on integrating, evaluating, and updating the technical information relevant to aging and license renewal from current and completed NRC and industry research programs. The major components for this project were selected according to the role they play in containing any fission products that may be released during an accident. The selected components include primary pressure boundary components, primary containments, cables and connectors, emergency diesel generators, and reactor pressure vessel supports. The degradation sites, mechanisms, stressors, and potential failure modes for these major components have been identified and evaluated. The results show that fatigue is a major degradation mechanism acting at several critical locations. This paper reviews the fatigue damage in the major components and identifies the unresolved safety issues relevant to aging and license-renewal considerations.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/7148345},
  journal      = {Trans. Am. Nucl. Soc.; (United States)},
number       = ,

  volume       = 55,

  place        = {United States},

  year         = {1987},

  month        = {1}

}

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