Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 3
Conference
·
OSTI ID:5378374
- comp.
This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. 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 twenty-two different papers presented by researchers from Belgium, Czechoslovakia, Germany, Italy, Japan, Russia, Spain, Sweden, The Netherlands 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. This report, Volume 3, discusses Aging and Life Extension; Structural and Seismic Research; and Mechanical Research. Twenty-two reports have been cataloged separately.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5378374
- Report Number(s):
- NUREG/CP-0091-Vol.3; CONF-8710111-Vol.3; ON: TI88006305
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
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Boiling Water Cooled
210200 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AFTER-HEAT REMOVAL
AGING
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BWR TYPE REACTORS
CONTAINMENT
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CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICAL PROPERTIES
MECHANICS
PIPES
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
REMOVAL
RESEARCH PROGRAMS
RESTRAINTS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SERVICE LIFE
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR
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
AFTER-HEAT REMOVAL
AGING
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICAL PROPERTIES
MECHANICS
PIPES
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RELIABILITY
REMOVAL
RESEARCH PROGRAMS
RESTRAINTS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SERVICE LIFE
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR