Published March 1985 | Version v1
Journal article Metadata-only

Comparisons of the RALIZA-2/02 two-phase flow model with experimental data

Creators

  • 1. Bylgarska Akademiya na Naukite, Sofia. Inst. po Yadrena Fizika i Yadrena Energetika

Description

The RALIZA-2 computer program was designed for thermal-hydraulic analysis of flow channel and fuel element of PWR/BWR at steady-state and transient conditions. A nonhomogeneous, nonequilibrium model of a two-phase flow and a two-dimensional heat conduction model of fuel rod are used in the program. A fully implicit integration scheme for both models is used. The steady-state constitutive correlations set is used. The void fraction, pre- and post-DNB heat transfer mechanism are compared with data. Also a loss of flow experiment was calculated and compared with nuclear heated rod bundle experimental data for typical PWRs. A very good agreement was obtained. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
85
Journal Issue
2
Series
Nucl. Eng. Des.
Journal Page Range
217-237
ISSN
0029-5493
CODEN
NEDEA

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
17036647
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Descriptors DEI
BWR TYPE REACTORS; COMPUTER CALCULATIONS; DEPARTURE NUCLEATE BOILING; FLOW MODELS; FUEL ELEMENT CLUSTERS; LOSS OF FLOW; MATHEMATICAL MODELS; PWR TYPE REACTORS; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
ACCIDENTS; BOILING; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; NUCLEATE BOILING; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS