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JOM

, Volume 53, Issue 7, pp 18–22 | Cite as

Embrittlement of nuclear reactor pressure vessels

  • G. R. Odette
  • G. E. Lucas
Overview Light Water Reactors

Abstract

Neutron irradiation embrittlement could limit the service life of some of the reactor-pressure vessels in existing commercial nuclear-power plants. Improved understanding the of the underlying causes of embrittlement has provided regulators and power-plant operators better estimates of vessel-operating margins. This article presents an overview of embrittlement, emphasizing the status of mechanistic understanding and models, and their role in increasing the reliability of vessel-integrity assessments. Finally, a number of outstanding issues and significant opportunities, including a new fracture-toughness master-curve method, are briefly described.

Keywords

DBTT Reactor Pressure Vessel Pressure Vessel Steel Nuclear Regulatory Commission Irradiation Embrittlement 
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

© TMS 2001

Authors and Affiliations

  • G. R. Odette
    • 1
  • G. E. Lucas
    • 1
  1. 1.the Department of Mechanical and Environmental Engineeringthe University of CaliforniaSanta Barbara

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