Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 2
Conference
·
OSTI ID:5488417
- 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 2 discusses Materials Engineering/Pressure Vessel Research and Radiation and Degraded Piping Effects; Non-destructive Evaluations; and Environmental Effects in Primary Systems. Twenty-three papers have been cataloged separately.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5488417
- Report Number(s):
- NUREG/CP-0091-Vol.2; CONF-8710111-Vol.2; ON: TI88006107
- Country of Publication:
- United States
- Language:
- English
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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
220500 -- Nuclear Reactor Technology-- Environmental Aspects
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
AGING
BOILERS
BWR TYPE REACTORS
CONTAINERS
COOLING SYSTEMS
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
ENERGY SYSTEMS
FRACTURE MECHANICS
FUEL CANS
IN-SERVICE INSPECTION
INSPECTION
IRRADIATION
LEADING ABSTRACT
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
NONDESTRUCTIVE TESTING
PIPES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TESTING
THERMAL SHOCK
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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
220500 -- Nuclear Reactor Technology-- Environmental Aspects
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ABSTRACTS
AGING
BOILERS
BWR TYPE REACTORS
CONTAINERS
COOLING SYSTEMS
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
ENERGY SYSTEMS
FRACTURE MECHANICS
FUEL CANS
IN-SERVICE INSPECTION
INSPECTION
IRRADIATION
LEADING ABSTRACT
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
NONDESTRUCTIVE TESTING
PIPES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MATERIALS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM GENERATORS
TESTING
THERMAL SHOCK
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS