Published August 2011 | Version v1
Journal article

Numerical simulation of thermal-hydraulic analysis for triplex horizontal thermal-shielding in CEFR

  • 1. China Institute of Atomic Energy, Beijing (China)

Description

China Experimental Fast Reactor (CEFR) is of pool-type, and the pool is divided into two plenums which are named hot plenum and cold plenum. Triplex horizontal thermal-shielding board, situated between hot plenum and cold plenum, is a cold boundary of hot plenum, and a hot boundary of cold plenum too. Thermal-hydraulic characteristic of the triplex horizontal thermal-shielding affects the temperature distribution of hot and cold plenums directly. The thermal-hydraulic characteristics of the 1/4 domain of the triplex horizontal thermal-shielding were numerically simulated when CEFR was in full power by using CFX 3-D program. The boundary temperature of cold plenum is 360 degree C, while hot plenum is 490 degree C or 516 degree C of two projects. The selected model is RNG k-ε model. Compared with the results in existence, the gained average temperature is less than the designed temperature, for calculating convection heat transfer. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
45
Journal Issue
8
Journal Page Range
p. 925-930
ISSN
1000-6931

Optional Information

Notes
6 figs., 2 tabs., 13 refs.