Management of the aging of critical safety-related concrete structures in light-water reactor plants

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6584458

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

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1. Oak Ridge National Lab., TN (USA)
2. Nuclear Regulatory Commission, Washington, DC (USA)

The Structural Aging Program has the overall objective of providing the USNRC with an improved basis for evaluating nuclear power plant safety-related structures for continued service. The program consists of a management task and three technical tasks: materials property data base, structural component assessment/repair technology, and quantitative methodology for continued-service determinations. Objectives, accomplishments, and planned activities under each of these tasks are presented. Major program accomplishments include development of a materials property data base for structural materials as well as an aging assessment methodology for concrete structures in nuclear power plants. Furthermore, a review and assessment of inservice inspection techniques for concrete materials and structures has been complete, and work on development of a methodology which can be used for performing current as well as reliability-based future condition assessment of concrete structures is well under way. 43 refs., 3 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6584458
• Report Number(s): CONF-9010185-3; ON: DE91001632; TRN: 90-035238
• Resource Relation: Conference: 18. water reactor safety information meeting, Gaithersburg, MD (USA), 22-24 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
NUCLEAR POWER PLANTS
AGING
PRESTRESSED CONCRETE
REINFORCED CONCRETE
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
CONTAINMENT SHELLS
DATA BASE MANAGEMENT
IN-SERVICE INSPECTION
PHYSICAL RADIATION EFFECTS
PROGRAM MANAGEMENT
PWR TYPE REACTORS
REACTOR SAFETY
SERVICE LIFE
SHIELDING
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINMENT
INSPECTION
MANAGEMENT
MATERIALS
NUCLEAR FACILITIES
POWER PLANTS
RADIATION EFFECTS
REACTORS
REINFORCED MATERIALS
SAFETY
THERMAL POWER PLANTS
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
990300 - Information Handling