Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 4, Separate effects/experiments and analyses, Source term uncertainty analysis, Integral systems testing, 2D/3D research

Conference · Mon Feb 01 04:00:00 EST 1988

OSTI ID:5316573

Weiss, A J ^[1]

---

1. 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. This document, Volume 4, discusses the following topics: Separate Effects/Experiments and Analyses; Source Term Uncertainty Analysis; Integral Systems Testing; and 2D/3D Research. Thirty reports have been documented separately.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5316573
• Report Number(s): NUREG/CP-0091-Vol.4; CONF-8710111-Vol.4; ON: TI88007181
• 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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABSTRACTS
ACCIDENTS
AEROSOLS
BOILERS
BWR TYPE REACTORS
CIRCULATING SYSTEMS
COLLOIDS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTROL EQUIPMENT
COOLING SYSTEMS
CORIUM
DATA
DATA COVARIANCES
DEPOSITS
DISPERSIONS
DOCUMENT TYPES
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EQUIPMENT
EXPERIMENTAL DATA
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LEADING ABSTRACT
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
SOLS
SOURCE TERMS
STEAM GENERATORS
T CODES
TRANSIENTS
TWO-PHASE FLOW
VALVES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS