Published May 1990 | Version v1
Journal article Metadata-only

A distribution parameter derived for rectangular channels and simulated subchannel geometry

Creators

  • 1. Maryland Univ., College Park, MD (USA). Dept. of Mechanical Engineering

Description

The distribution parameter of the drift-flux model has been developed for a rectangular channel and a simulated boiling water reactor (BWR) subchannel. The void fraction prediction by the subchannel drift-flux code CANAL is demonstrated for heated rectangular channels. Intrasubchannel flow and void profiles are considered for subchannel model development. Distribution parameter C0 is found to be very sensitive to variation of the geometric parameters and subchannel types. Since void fraction measurements corresponding to the rectangular subchannel of a BWR rod bundle are unavailable at present, assessment of the derived models remains to be performed

Additional details

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
90
Journal Issue
2
Series
Nucl. Technol.
Journal Page Range
125-140
ISSN
0029-5450
CODEN
NUTYB

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22009723
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BWR TYPE REACTORS; C CODES; FUEL ELEMENT CLUSTERS; GEOMETRY; MULTI-PARAMETER ANALYSIS; REACTOR CHANNELS; SPECIFICATIONS; VOID FRACTION
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS