Published November 1982 | Version v1
Journal article Metadata-only

Boiling and dryout predictions in postaccident heat removal situations

Creators

  • 1. von Karman Institute for Fluid Dynamics, Chaussee de Waterloo, 72 B-1640 Rhode Saint Genese

Description

A new model is proposed to predict the formation and influence of channels on the behavior of the debris bed related to the postaccident heat removal situation in fast breeder nuclear reactors cooled by liquid sodium. A two-dimensional dryout numerical prediction based on the spouting occurrence shows a complete agreement with the results of in-pile tests D2, D3, and D4 at Sandia National Laboratories

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
59
Journal Issue
2
Series
Nucl. Technol.
Journal Page Range
234-237
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15073074
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AFTER-HEAT REMOVAL; BOILING; DRYOUT; FISSION PRODUCTS; FORECASTING; IN PILE LOOPS; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR CORE DISRUPTION; SANDIA LABORATORIES; SODIUM; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
ACCIDENTS; ALKALI METALS; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; SANDIA NATIONAL LABORATORIES; US AEC; US DOE; US ERDA; US ORGANIZATIONS