Seventeenth water reactor safety information meeting: Proceedings

Conference · Thu Mar 01 04:00:00 EST 1990

OSTI ID:7077729

Weiss, A. J. ^[1]

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1. Brookhaven National Lab., Upton, NY (USA); comp.

This three-volume report contains 84 papers out of the 111 that were presented at the Seventeenth Water Reactor Safety Information Meeting held at the Holiday Inn Crowne Plaza, Rockville, Maryland, during the week of October 23--25, 1989. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included ten different papers presented by researchers from France, Germany, Japan, Norway and the United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Each report will be cataloged individually.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 7077729
• Report Number(s): NUREG/CP-0105-Vol.3; CONF-8910222--Vol.3; ON: TI90008997
• Country of Publication: United States
• Language: English

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
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
AGING
BWR TYPE REACTORS
CONTAINERS
CONTROL EQUIPMENT
COOLING SYSTEMS
DOCUMENT TYPES
EMERGENCY PLANS
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
ENGINEERING
EQUIPMENT
FAILURE MODE ANALYSIS
FLOW REGULATORS
FUNCTIONS
IRRADIATION
LEADING ABSTRACT
LICENSING
MAN-MACHINE SYSTEMS
MANAGEMENT
OCCUPATIONAL SAFETY
OPERATION
PERFORMANCE TESTING
PIPES
PROBABILITY
PROGRAM MANAGEMENT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR LICENSING
REACTOR OPERATION
REACTOR SAFETY
REACTOR VESSELS
REACTORS
REGULATIONS
RELIABILITY
RESEARCH PROGRAMS
SAFETY
SEISMIC EFFECTS
STRENGTH FUNCTIONS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TECHNOLOGY ASSESSMENT
TESTING
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS