Published June 2011 | Version v1
Journal article Metadata-only

Numerical analysis of natural convection in HTR-PM reactor cabin

Creators

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing (China)

Description

In order to study natural convection in HTR-PM reactor cabin, radiation coefficient, radiation model, flow model and near wall treatment were discussed to explore suitable model used for numerical analysis of natural convection in HTR-PM reactor cabin. Using this model, temperature difference of inner and outer wall, ratio of gap and height in annulus, ratio of cooling wall height in annulus, ratio of inner and outer wall radius and temperature distribution were analyzed. Correlations were given for some factors. All these will be reference for design and analysis of HTR-PM reactor cabin. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
45
Journal Issue
6
Journal Page Range
p. 657-661
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
45068288
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ANNULAR SPACE; CHINA; COOLING; CORRELATIONS; DESIGN; FLOW MODELS; HEIGHT; HTR REACTOR; NATURAL CONVECTION; NUMERICAL ANALYSIS; PEBBLE BED REACTORS; TEMPERATURE DISTRIBUTION; WALLS
Descriptors DEC
ASIA; CONFIGURATION; CONVECTION; DIMENSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; HEAT TRANSFER; HOMOGENEOUS REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MASS TRANSFER; MATHEMATICAL MODELS; MATHEMATICS; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; SPACE; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 figs., 1 tabs., 12 refs.