The development of design procedures to prevent the occurrence of unexpected and sudden failures in engineering structures and components has been the subject of intensive activity for many years. The Pressure Vessel Research Committee (PVRC) of the Welding Research Council formed a Task Group under the Planning and Evaluation Committee to review current knowledge and prepare recommendations on toughness requirements for ferritic materials in nuclear power plant components. The recommendations were requested from PVRC by the ASME Boiler and Pressure Vessel Committee for their use in considering any revisions to the requirements of Section III--Nuclear Power Plant Components. Specifically, the Task Group undertook to recommend, on the basis of current knowledge, criteria for ferritic-material-toughness requirements for pressure retaining components of the reactor coolant pressure boundary operating below 700 deg F. These criteria, when used in addition to the stress limits allowed by the ASME Code, should permit the establishment of safe procedures for operating nuclear reactor components under normal, upset, and testing conditions; emergency and faulted conditions should be considered on a case basis. In January 1972, the ASME Boiler and Pressure Vessel Committee approved revisions to the toughness requirements of Section III of the Code which were based on (but not identical to) the recommendations in this report.

  • Corporate Authors:

    Welding Research Council

    345 East 47th Street
    New York, NY  United States  10017
  • Publication Date: 1972-8

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Filing Info

  • Accession Number: 00035917
  • Record Type: Publication
  • Source Agency: Welding Research Council
  • Files: TRIS
  • Created Date: Oct 13 1972 12:00AM