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Ductile Fracture Analysis and Safety of Nuclear Pressure Vessels

  • F. J. Loss
Part of the Sagamore Army Materials Research Conference Proceedings book series (SAMC, volume 24)

Abstract

The past two decades have witnessed the development of commercial nuclear power into a mature industry. Because of the potential for release of radioactive materials there has been a parallel growth in procedures for the prevention of fracture in nuclear pressure vessles and associated components. A catalyst to this development has been the discovery of radiation embrittlement in the ferritic steels used in pressure vessel construction. This chapter reviews current fracture analysis methodology for nuclear vessels from the viewpoint of linear elastic fracture mechanics and code procedures which are applied to assure structural integrity.

Keywords

Crack Extension Linear Elastic Fracture Mechanic Electric Power Research Institute Reactor Pressure Vessel Nuclear Regulatory Commission 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Plenum Press, New York 1980

Authors and Affiliations

  • F. J. Loss
    • 1
  1. 1.Naval Research LaboratoryUSA

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