Management of aging of nuclear power plant containment structures

Conference · Mon Jun 01 04:00:00 EDT 1998

OSTI ID:663355

Naus, D; Oland, C B ^[1]; Ellingwood, B ^[2]; Norris, W E; Graves, III, H L ^[3]

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1. Oak Ridge National Lab., TN (United States). Engineering Technology Div.
2. Johns Hopkins Univ., Baltimore, MD (United States). Dept. of Civil Engineering
3. Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research

Research addressing aging management of nuclear power plant concrete and steel containment structures is summarized. Accomplishments related to concrete containment structures include formation of a materials` property database; an aging assessment methodology to identify critical structures and degradation factors; guidelines and evaluation criteria for use in condition assessments; and a time-dependent reliability-based methodology for condition assessments and estimations of future performance. Under the steel containments and liners activity, a degradation assessment methodology has been developed, mathematical models that describe time-dependent changes in the containment due to aggressive environmental factors have been identified, and statistical data supporting the use of these models in time-dependent reliability analysis have been summarized.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 663355
• Report Number(s): ORNL/CP--96731; CONF-980915--; ON: DE98005757
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AGING
BWR TYPE REACTORS
CONCRETES
CONTAINMENT SYSTEMS
MATHEMATICAL MODELS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
SAFETY ANALYSIS
SERVICE LIFE
STEELS