Proceedings of the US Nuclear Regulatory Commission nineteenth water reactor safety information meeting

Conference · Wed Apr 01 04:00:00 EST 1992

OSTI ID:5425059

Weiss, A J ^[1]

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

This three-volume report contains 83 papers out of the 108 that were presented at the Nineteenth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 28--30, 1991. 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 14 different papers presented by researchers from Canada, Germany, France, Japan, Sweden, Taiwan, and USSR. This document, Volume 1, presents papers on: pressure vessel and piping integrity, metallurgy and nondestructive examination; aging and components; and probabilistic risk assessment. The individual papers have been cataloged separately.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 5425059
• Report Number(s): NUREG/CP-0119-Vol.1; CONF-911079--Vol.1; ON: TI92013798
• 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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
AGING
BWR TYPE REACTORS
CONTAINERS
DOCUMENT TYPES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LEADING ABSTRACT
MATERIALS TESTING
MECHANICS
MEETINGS
METALLURGY
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
POWER REACTORS
PRESSURE VESSELS
PROBABILISTIC ESTIMATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SYSTEMS ANALYSIS
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS