Aging of concrete containment structures in nuclear power plants

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5299914

Naus, D J; Oland, C B ^[1]; Ellingwood, B; Mori, Yasuhiro ^[2]; Arndt, E G ^[3]

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1. Oak Ridge National Lab., TN (United States)
2. Johns Hopkins Univ., Baltimore, MD (United States)
3. Nuclear Regulatory Commission, Washington, DC (United States)

Concrete structures play a vital role in the safe operation of all light-water reactor plants in the US Pertinent concrete structures are described in terms of their importance design, considerations, and materials of construction. Degradation factors which can potentially impact the ability of these structures to meet their functional and performance requirements are identified. Current inservice inspection requirements for concrete containments are summarized. A review of the performance history of the concrete components in nuclear power plants is provided. A summary is presented. A summary is presented of the Structural Aging (SAG) Program being conducted at the Oak Ridge National Laboratory for the US Nuclear Regulatory Commission. The SAG Program is addressing the aging management of safety-related concrete structures in nuclear power plants for the purpose of providing improved bases for their continued service. The program consists of a management task and three technical tasks: materials property data base, structural component assessment/repair technologies, and quantitiative methodology for continued service conditions. Objectives and a summary of accomplishments under each of these tasks are presented.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5299914
• Report Number(s): CONF-920541-2; ON: DE92014330
• Resource Relation: Conference: 5. workshop on containment integrity for nuclear power plants, Washington, DC (United States), 12-14 May 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT SYSTEMS
CONCRETES
AGING
CONTAINMENT BUILDINGS
PWR TYPE REACTORS
FAILURES
IN-SERVICE INSPECTION
MAINTENANCE
REACTOR SAFETY
RELIABILITY
BUILDING MATERIALS
BUILDINGS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
INSPECTION
MATERIALS
POWER REACTORS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled