Aging research information conference: Abstracts of papers
Conference
·
OSTI ID:10130016
- comp.
This report contains abstracts of papers to be presented at the Aging Research Information Conference held at the Holiday Inn Crowne Plaza in Rockville, Maryland, on March 24--27, 1992. This conference is held to disseminate research results in the area of nuclear power plant aging from programs sponsored by the Office of Nuclear Regulatory Research, US Nuclear Regulatory Commission. The conference will also provide an opportunity for engineers and scientists from around the world to exchange technical information and discuss future international cooperation. The abstracts appear in the order in which they will be presented at the conference, and they are grouped by technical session. The full papers and the agenda for the conference will be published as separate documents.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10130016
- Report Number(s):
- NUREG/CP--0121; CONF-920375--Absts.; ON: TI92008147
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
36 MATERIALS SCIENCE
360103
360105
AGING
BWR TYPE REACTORS
CONTROL ROD DRIVES
CORROSION
CORROSION AND EROSION
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
EMBRITTLEMENT
EROSION
FAILURES
FATIGUE
INSPECTION
MAINTENANCE
MECHANICAL PROPERTIES
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR VESSELS
RISK ASSESSMENT
VALVES
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
36 MATERIALS SCIENCE
360103
360105
AGING
BWR TYPE REACTORS
CONTROL ROD DRIVES
CORROSION
CORROSION AND EROSION
ELECTRIC CABLES
ELECTRICAL EQUIPMENT
EMBRITTLEMENT
EROSION
FAILURES
FATIGUE
INSPECTION
MAINTENANCE
MECHANICAL PROPERTIES
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR VESSELS
RISK ASSESSMENT
VALVES