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Published: 2015-09-30
Abstract Views: 213
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DOI: https://doi.org/10.53747/jnst.v5i3.196
Issue
Vol. 5 No. 3 (2015)
Section
Articles
How to Cite
Hoang , M. G., Hoang , T. H., & Nguyen , H. T. (2015). Multi codes and multi-scale analysis for void fraction prediction in hot channel for VVER-1000/V392. Nuclear Science and Technology, 5(3), 19-31. https://doi.org/10.53747/jnst.v5i3.196

Multi codes and multi-scale analysis for void fraction prediction in hot channel for VVER-1000/V392

Hoang Minh Giang1, Hoang Tan Hung1, Nguyen Huu Tiep2
1 Nuclear Safety Center, Institute for Nuclear Science and Technology
2 Nuclear Power Center, Institute for Nuclear Science and Technology

Main Article Content

Abstract

Recently, an approach of multi codes and multi-scale analysis is widely applied to study core thermal hydraulic behavior such as void fraction prediction. Better results are achieved by using multi codes or coupling codes such as PARCS and RELAP5. The advantage of multi-scale analysis is zooming of the interested part in the simulated domain for detail investigation.  Therefore, in this study, the multi codes between MCNP5, RELAP5, CTF and also the multi-scale analysis based RELAP5 and CTF are applied to investigate void fraction in hot channel of VVER-1000/V392 reactor. Since VVER-1000/V392 reactor is a typical advanced reactor that can be considered as the base to develop later VVER-1200 reactor, then understanding core behavior in transient conditions is necessary in order to investigate VVER technology. It is shown that the item of near wall boiling,  in RELAP5 proposed by Lahey mechanistic method may not give enough accuracy of void fraction prediction as smaller scale code as CTF.

Article Details

Keywords

VVER, CTF, RELAP5, multi-scale, void fraction, hot channel

References

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