Transactions of the seventeenth water reactor safety information meeting
Conference
·
OSTI ID:5655157
This report contains summaries of papers on reactor safety research to be presented at the 17th Water Reactor Safety Information Meeting at the Holiday Inn Crowne Plaza in Rockville, Maryland, October 23--25, 1989. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual papers have been cataloged separately.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
- Sponsoring Organization:
- NRC
- OSTI ID:
- 5655157
- Report Number(s):
- NUREG/CP-0104; CONF-8910222--Summs.; ON: TI90000746
- 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
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
AGING
ALLOYS
AUXILIARY SYSTEMS
BLACKOUTS
BOILERS
BUILDING MATERIALS
BWR TYPE REACTORS
COMPUTER CODES
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
CONTROL ROOMS
CORIUM
CRACKS
DOCUMENT TYPES
ELEMENTS
EMERGENCY PLANS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FAILURES
FISSION PRODUCT RELEASE
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
HYDROGEN
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
M CODES
MAINTENANCE
MANAGEMENT
MATERIALS
MECHANICS
MITIGATION
NONMETALS
PIPES
PROGRAM MANAGEMENT
PWR TYPE REACTORS
R CODES
RADIATION EFFECTS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTOR VESSELS
REACTORS
RELIABILITY
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SCRAM
SEISMIC EFFECTS
SEISMICITY
SHUTDOWN
STEAM GENERATORS
STEELS
T CODES
TRANSIENTS
TUBES
V CODES
VALVES
VAPOR GENERATORS
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
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
AGING
ALLOYS
AUXILIARY SYSTEMS
BLACKOUTS
BOILERS
BUILDING MATERIALS
BWR TYPE REACTORS
COMPUTER CODES
CONCRETES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
CONTROL ROOMS
CORIUM
CRACKS
DOCUMENT TYPES
ELEMENTS
EMERGENCY PLANS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FAILURES
FISSION PRODUCT RELEASE
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
HYDROGEN
IRON ALLOYS
IRON BASE ALLOYS
LEADING ABSTRACT
M CODES
MAINTENANCE
MANAGEMENT
MATERIALS
MECHANICS
MITIGATION
NONMETALS
PIPES
PROGRAM MANAGEMENT
PWR TYPE REACTORS
R CODES
RADIATION EFFECTS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTOR VESSELS
REACTORS
RELIABILITY
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SCRAM
SEISMIC EFFECTS
SEISMICITY
SHUTDOWN
STEAM GENERATORS
STEELS
T CODES
TRANSIENTS
TUBES
V CODES
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS