Transactions of the fifteenth water reactor safety information meeting

Technical Report · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:6056345

Weiss, A J ^[1]

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1. comp.

This report contains summaries of paper on reactor safety research to be presented at the 15th Water Reactor Safety Information Meeting held at the National Bureau of Standards in Gaithersburg, Maryland, October 26-29, 1987. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues are included from the Office of Nuclear Reactor Regulation, USNRC, in addition to summaries of invited papers that cover the highlights of reactor safety research conducted by the Department of Energy (DOE), the electric utilities through the Electric Power Research Institute (EPRI), the nuclear industry, and the research of government and industry in Europe and Japan. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
• OSTI ID: 6056345
• Report Number(s): NUREG/CP-0090; ON: DE88900097
• 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
210500 -- Power Reactors
Breeding
210700 -- Nuclear Power Plants-- Regulation & Licensing
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACOUSTIC EMISSION TESTING
ACOUSTIC TESTING
AEROSOLS
AGING
ALLOYS
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
BOILERS
BORON
BREEDER REACTORS
BWR TYPE REACTORS
C CODES
CARBON STEELS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CLEANING
COLLOIDS
COMPUTER CODES
CONTAINMENT
CONTROL EQUIPMENT
CONTROL SYSTEMS
CORIUM
CORROSION
CORROSION RESISTANT ALLOYS
CRACKS
DATA COVARIANCES
DECOMMISSIONING
DECONTAMINATION
DESIGN
DISPERSIONS
ELEMENTS
EMBRITTLEMENT
ENERGY TRANSFER
EPITHERMAL REACTORS
EQUIPMENT
EXPERT SYSTEMS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
FRACTURE MECHANICS
GROUND MOTION
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
HYDROGEN
I CODES
IN-SERVICE INSPECTION
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
L CODES
LICENSING
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
M CODES
MAINTENANCE
MANAGEMENT
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
MOTION
NONDESTRUCTIVE TESTING
NONMETALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
PIPES
POWER PLANTS
PUBLIC OPINION
PUBLIC POLICY
PUMPS
PWR TYPE REACTORS
QUENCHING
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR DECOMMISSIONING
REACTOR LICENSING
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTORS
REGULATIONS
RELIABILITY
RESEARCH PROGRAMS
RISK ASSESSMENT
S CODES
SAFETY
SEISMIC EFFECTS
SEMIMETALS
SERVICE LIFE
SOLS
SOURCE TERMS
STAINLESS STEELS
STEAM GENERATORS
STEEL-ASTM-A533-B
STEELS
STRAIN RATE
STRESS ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
T CODES
TESTING
THERMAL POWER PLANTS
TUBES
TWO-PHASE FLOW
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS