CFX simulation of a horizontal heater rods test
- 1. Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)
Description
In this study a CFD simulation of a horizontal heater rods test (CS28-2) has been performed with the CFX-10 code and it has been compared with an experiment in order to develop a post-blowdown modeling of a CANDU fuel channel during a large break loss of coolant accident (LBLOCA). The CS28-2 experiment is one of three series of experiments to simulate the fuel channel at a high temperature and a low steam flow rate which may occur in severe accident conditions such as a LBLOCA of CANDU reactors. Since radiation heat transfer is dominant in the CS28-2 experiment, a benchmark problem of radiation heat transfer for the same geometry as the CS28-2 is carried out first to assess the radiation model by CFX-10, to confirm whether CFX-10 can be applied to a complex fuel geometry or not. And, the CFD study of the CS28-2 has been performed with the aim to simulate the steady-state condition of the CS28-2. These steady-state calculation results will be used for the initial conditions of the transient simulation
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2007.02.045Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2007.02.045;
- PII
- S0029-5493(07)00341-X;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 3
- Journal Page Range
- p. 522-529
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39049082
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; BLOWDOWN; DOUGLAS POINT ONTARIO REACTOR; FLOW RATE; FUELS; GEOMETRY; HEAT TRANSFER; HEATERS; LOSS OF COOLANT; SIMULATION; STEADY-STATE CONDITIONS; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- ACCIDENTS; CANDU TYPE REACTORS; ENERGY TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MATHEMATICS; NATURAL URANIUM REACTORS; PHWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.