Proceedings of the Aging Research Information Conference
Conference
·
OSTI ID:6982780
- comp.
This report presents the proceedings of the Aging Research Information Conference held at the Holiday Inn Crowne Plaza in Rockville, Maryland, on March 24--27, 1992. This conference was 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 papers and talks appear in the order in which they were presented at the conference, and they are grouped by technical session in two volumes. This document, Volume 1 contains the proceedings of March 24 and 25, while Volume 2 contains the proceedings of March 26 and 27.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 6982780
- Report Number(s):
- NUREG/CP-0122-Vol.1; CONF-920375--Vol.1; ON: TI92041279
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
AGING
BWR TYPE REACTORS
CIRCUIT BREAKERS
CONTAINERS
CONTROL EQUIPMENT
CONTROL ROD DRIVES
COOLING SYSTEMS
DOCUMENT TYPES
ELECTRIC BATTERIES
ELECTRIC GENERATORS
ELECTRICAL EQUIPMENT
ELECTROCHEMICAL CELLS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
EQUIPMENT PROTECTION DEVICES
FATIGUE
FLOW REGULATORS
IN-SERVICE INSPECTION
INSPECTION
LEADING ABSTRACT
MAINTENANCE
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RISK ASSESSMENT
SAFETY
SUPPORTS
SURVEILLANCE
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
TRANSFORMERS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
AGING
BWR TYPE REACTORS
CIRCUIT BREAKERS
CONTAINERS
CONTROL EQUIPMENT
CONTROL ROD DRIVES
COOLING SYSTEMS
DOCUMENT TYPES
ELECTRIC BATTERIES
ELECTRIC GENERATORS
ELECTRICAL EQUIPMENT
ELECTROCHEMICAL CELLS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
EQUIPMENT PROTECTION DEVICES
FATIGUE
FLOW REGULATORS
IN-SERVICE INSPECTION
INSPECTION
LEADING ABSTRACT
MAINTENANCE
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RISK ASSESSMENT
SAFETY
SUPPORTS
SURVEILLANCE
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
TRANSFORMERS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS