Eighteenth water reactor safety information meeting

Conference · Mon Apr 01 00:00:00 EST 1991

OSTI ID:5772642

Weiss, A J ^[1]

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

This three-volume report contains 100 papers out of the 128 that were presented at the Eighteenth Water Reactor Safety Information Meeting held at the Holiday Inn Crowne Plaza, Rockville, Maryland, during the week of October 22--24, 1990. 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 16 different papers presented by researchers from Denmark, Egypt, Germany, IAEA, Italy, Japan, Norway, Taiwan, UK and USSR. This document, Volume 3, includes papers on pressure vessel integrity, piping and nondestructive examinations; and components and aging. Each paper has been individually cataloged.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5772642
• Report Number(s): NUREG/CP-0114-Vol.3; CONF-9010185-Vol.3; ON: TI91011806; TRN: 91-019109
• Resource Relation: Conference: 18. water reactor safety information meeting, Rockville, MD (USA), 22-24 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
REACTOR SAFETY
NUCLEAR POWER PLANTS
PIPES
PRESSURE VESSELS
REACTOR COMPONENTS
NONDESTRUCTIVE ANALYSIS
FRACTURE PROPERTIES
PWR TYPE REACTORS
AGING
REACTOR MATERIALS
CHARPY TEST
CIRCUIT BREAKERS
CORROSION
CRACK PROPAGATION
CRACKS
ELECTRIC CABLES
EMBRITTLEMENT
FAILURES
FATIGUE
FRACTURE MECHANICS
IMPACT SHOCK
IMPACT STRENGTH
IN-SERVICE INSPECTION
LEADING ABSTRACT
LOSS OF COOLANT
METALLURGY
MICROSTRUCTURE
NEUTRON FLUENCE
NONDESTRUCTIVE TESTING
PUMPS
RADIATION EFFECTS
RELAYS
RESEARCH PROGRAMS
STAINLESS STEELS
STEAM GENERATORS
THREE MILE ISLAND-2 REACTOR
TUBES
VALVES
WEAR
WELDED JOINTS
ABSTRACTS
ACCIDENTS
ALLOYS
BOILERS
CABLES
CHEMICAL ANALYSIS
CHEMICAL REACTIONS
CONDUCTOR DEVICES
CONTAINERS
CONTROL EQUIPMENT
CRYSTAL STRUCTURE
DESTRUCTIVE TESTING
DOCUMENT TYPES
ELECTRICAL EQUIPMENT
ENRICHED URANIUM REACTORS
EQUIPMENT
EQUIPMENT PROTECTION DEVICES
FLOW REGULATORS
HIGH ALLOY STEELS
IMPACT TESTS
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
STEELS
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties
360105 - Metals & Alloys- Corrosion & Erosion
360106 - Metals & Alloys- Radiation Effects