Aging of steel containments and liners in nuclear power plants

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Aging of the containment pressure boundary in light water reactor plants is being addressed to understand the significant factors relating occurrence of corrosion efficacy of inspection and structural capacity reduction of steel containments and liners of concrete containments. and to make recommendations on use of risk models in regulatory decisions. Current regulatory in-service inspection requirements are reviewed and a summary of containment related degradation experience is presented. Current and emerging nondestructive examination techniques and a degradation assessment methodology for characterizing and quantifying the amount of damage present are described. Quantitative tools for condition assessment of aging structures using time dependent ... continued below

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17 p.

Creation Information

Naus, D.J.; Oland, C.B.; Ellingwood, B. & Norris, W.E. January 1, 1998.

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  • Naus, D.J.
  • Oland, C.B. Oak Ridge National Lab., TN (United States). Engineering Technology Div.
  • Ellingwood, B. Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering
  • Norris, W.E. Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research

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Description

Aging of the containment pressure boundary in light water reactor plants is being addressed to understand the significant factors relating occurrence of corrosion efficacy of inspection and structural capacity reduction of steel containments and liners of concrete containments. and to make recommendations on use of risk models in regulatory decisions. Current regulatory in-service inspection requirements are reviewed and a summary of containment related degradation experience is presented. Current and emerging nondestructive examination techniques and a degradation assessment methodology for characterizing and quantifying the amount of damage present are described. Quantitative tools for condition assessment of aging structures using time dependent structural reliability analysis methods are summarized. Such methods provide a framework for addressing the uncertainties attendant to aging in the decision process. Results of this research provide a means for establishing current and estimating future structural capacity margins of containments, and to address the significance of incidences of reported containment degradation.

Physical Description

17 p.

Notes

INIS; OSTI as DE98005043

Source

  • 1998 ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998

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  • Other: DE98005043
  • Report No.: ORNL/CP--96080
  • Report No.: CONF-980708--
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 650369
  • Archival Resource Key: ark:/67531/metadc702444

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • January 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

Description Last Updated

  • April 7, 2016, 7:32 p.m.

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Naus, D.J.; Oland, C.B.; Ellingwood, B. & Norris, W.E. Aging of steel containments and liners in nuclear power plants, article, January 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc702444/: accessed December 11, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.