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
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 45068337
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CEFR REACTOR; COMPUTERIZED SIMULATION; CONVECTION; SHIELDS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
- Descriptors DEC
- ENERGY TRANSFER; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION
Optional Information
- Notes
- 6 figs., 2 tabs., 13 refs.