| Issue |
2014
SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
|
|
|---|---|---|
| Article Number | 01204 | |
| Number of page(s) | 6 | |
| Section | 1. Computational Nuclear Applications: b. Thermalhydraulics | |
| DOI | https://doi.org/10.1051/snamc/201401204 | |
| Published online | 06 June 2014 | |
Numerical Analysis on the Calandria Tubes in the Moderator of a Heavy Water Reactor Using OpenFOAM and Other Codes
1 Kunsan National University, 558 Daehak-ro, Gunsan-shi, Jeonbuk 573-701, Korea
2 Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Korea
* Corresponding Author, E-mail: smchang@kunsan.ac.kr
CANDU, a prototype of heavy water reactor is modeled for the moderator system with porous media buoyancy-effect heat-transfer turbulence model. OpenFOAM, a set of C++ classes and libraries developed under the object-oriented concept, is selected as the tool of numerical analysis. The result from this computational code is compared with experiments and other commercial code data through ANSYS-CFX and COMSOL Multi-physics. The three-dimensional code concerning buoyancy force, turbulence, and heat transfer is tested and shown to be successful for the analysis of thermo-hydraulic system of heavy water reactors.
Key words: CANDU reactor / Moderator / Calandria tube / OpenFOAM / ANSYS-CFX / COMSOL
© Owned by the authors, published by EDP Sciences, 2014