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Proactive Management of Materials Degradation - A Review of Principles and Programs.


DE2008939352

Publication Date 2008
Personal Author Bond, L. J.; Doctor, S. R.; Taylor, T. T.
Page Count 172
Abstract The U.S. Nuclear Regulatory Commission (NRC) has undertaken a program to lay the technical foundation for defining proactive actions so that future degradation of materials in light water reactors (LWRs) is limited and, thereby, does not diminish either the integrity of important LWR components or the safety of operating plants. This technical letter report was prepared by staff at Pacific Northwest National Laboratory in support of the NRC Proactive Management of Materials Degradation (PMMD) program and relies heavily on work that was completed by Dr. Joseph Muscara and documented in NUREG/CR-6923. This report concisely explains the basic principles of PMMD and its relationship to prognostics, provides a review of programs related to PMMD being conducted worldwide, and provides an assessment of the technical gaps in PMMD and prognostics that need to be addressed. This technical letter report is timely because the majority of the U.S. reactor fleet is applying for license renewal, and many plants are also applying for increases in power rating. Both of these changes could increase the likelihood of materials degradation and underline, therefore, the interest in proactive management in the future.
Keywords
  • Degradation
  • Management
  • Water cooled reactors
  • Reactor materials
  • Material testing
Source Agency
  • Technical Information Center Oak Ridge Tennessee
Corporate Authors Pacific Northwest National Lab., Richland, WA.; Department of Energy, Washington, DC.
Supplemental Notes Sponsored by Department of Energy, Washington, DC.
Document Type Technical Report
NTIS Issue Number 200907
Contract Number
  • DE-AC05-76RL01830
Proactive Management of Materials Degradation - A Review of Principles and Programs.
Proactive Management of Materials Degradation - A Review of Principles and Programs.
DE2008939352

  • Degradation
  • Management
  • Water cooled reactors
  • Reactor materials
  • Material testing
  • Technical Information Center Oak Ridge Tennessee
  • DE-AC05-76RL01830
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