2014SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
|Number of page(s)||2|
|Section||5. Poster Session: a. Computational Nuclear Applications|
|Published online||23 July 2014|
Performance Assessment of the Commercial CFD Software for the Prediction of the PWR Internal Flow*
1 Korea Institute of Nuclear Safety, Daejon, Republic of Korea
2 ANFLUX Inc., Seoul, Republic of Korea
*Corresponding Author, E-mail: email@example.com
As the computer hardware technology develops the license applicants for nuclear power plant use the commercial CFD software with the aim of reducing the excessive conservatism associated with using simplified and conservative analysis tools. Even if some of CFD software developers and its users think that a state of the art CFD software can be used to solve reasonably at least the single-phase nuclear reactor safety problems, there is still the limitations and the uncertainties in the calculation result. From a regulatory perspective, Korea Institute of Nuclear Safety (KINS) has been presently conducting the performance assessment of the commercial CFD software for the nuclear reactor safety problems. In this study, in order to examine the prediction performance of the commercial CFD software with the porous model in the analysis of the scale-down APR+ (Advanced Power Reactor Plus) internal flow, simulation was conducted with the on-board numerical models in ANSYS CFX R.14 and FLUENT R.14. It was concluded that depending on the CFD software the internal flow distribution of the scale-down APR+ was locally somewhat different. Although there was a limitation in estimating the prediction performance of the commercial CFD software due to the limited number of the measured data, CFX R.14 showed the more reasonable predicted results in comparison with FLUENT R.14. Meanwhile, due to the difference of discretization methodology, FLUENT R.14 required more the computational memory than CFX R.14 for the same grid system. Therefore the CFD software suitable to the available computational resource should be selected for the massive parallel computation.
Key words: Flow Similarity / Porous Assumption / Reactor Internal Flow / Turbulent Flow
This corrected version replaces the article Performance Assessment of the Commercial CFD Software for the Prediction of the Reactor Internal Flow, SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 05106 (2014), DOI: 10.1051/snamc/201405106, which has been formally withdrawn.
© Owned by the authors, published by EDP Sciences, 2014