Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

Conference · Fri Apr 01 04:00:00 EST 1994

OSTI ID:10147720

Monteleone, S ^[1]

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

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. 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 papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and 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. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10147720
• Report Number(s): NUREG/CP--0133-Vol.1; CONF-931079--Vol.1; ON: TI94011188
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
AGING
BWR TYPE REACTORS
CONTAINMENT
ENVIRONMENTAL ENGINEERING
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
INTERNATIONAL ORGANIZATIONS
LEADING ABSTRACT
LOSS OF COOLANT
MANAGEMENT
MEETINGS
NUCLEAR POWER PLANTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PROBABILISTIC ESTIMATION
PROCEEDINGS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
SEISMIC EFFECTS
SYSTEMS ANALYSIS