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 00:00:00 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; TRN: 94:011980
• Resource Relation: Conference: 21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993; Other Information: PBD: Apr 1994
• Country of Publication: United States
• Language: English

Related Subjects

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