Published December 1987 | Version v1
Journal article Metadata-only

An assessment of steam-explosion-induced containment failure. Part II: Premixing limits

Creators

  • 1. Univ. of California, Dept. of Chemical and Nuclear Engineering, Santa Barbara, CA (USA)

Description

The issues of transient and two-dimensional effects on fuel-coolant mixing in the lower plenum of a pressurized water reactor are addressed and resolved. Strong coolant depletion phenomena within fuel regions are analytically demonstrated. Quantification of premixtures under a variety of contact modes and conditions is used to specify the probable ranges of fuel mass available to participate in an explosion as a function of the core failure (melt pour) area

Additional details

Publishing Information

Journal Title
Nucl. Sci. Eng.
Journal Volume
97
Journal Issue
4
Series
Nucl. Sci. Eng.
Journal Page Range
282-295
ISSN
0029-5639
CODEN
NSENA

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19084552
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ANALYTICAL SOLUTION; CONTAINMENT SYSTEMS; EXPLOSIONS; FAILURE MODE ANALYSIS; FUEL-CLADDING INTERACTIONS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY EXPERIMENTS; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
ACCIDENTS; CONTAINMENT; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS