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Published: 2016-06-30
Abstract Views: 184
Views PDF: 13
DOI: https://doi.org/10.53747/jnst.v6i2.153
Issue
Vol. 6 No. 2 (2016)
Section
Articles
How to Cite
Ta , D. L., Nguyen , H. H., Nguyen , T. K., Tran , V. T., & Nguyen , H. T. (2016). Coulped neutronics/thermal-hydraulics calculation of VVER-1000 fuel assembly. Nuclear Science and Technology, 6(2), 31-38. https://doi.org/10.53747/jnst.v6i2.153

Coulped neutronics/thermal-hydraulics calculation of VVER-1000 fuel assembly

Ta Duy Long1, Nguyen Huy Hiep1, Nguyen Tuan Khai1, Tran Vinh Thanh1, Nguyen Huu Tiep1
1 Institute for Nuclear Science and Technology 179 Hoang Quoc Viet, Ha Noi

Main Article Content

Abstract

This paper presents a computational scheme using MCNP5 and COBRA-EN for coupling neutronics/thermal hydraulics calculation of a VVER-1000 fuel assembly. A master program was written using the PERL script language to build the corresponding inputs for the MCNP5 and COBRA-EN calculations and to manage the coupling scheme. The hexagonal coolant channels have been used in the thermal hydraulics model using CORBRA-EN to simplify the coupling scheme. The results of two successive iterations were compared with an assigned convergence criterion and the loop calculation can be broken when the convergence criterion is satisfied. Numerical calculation has been performed based on a UO2fuel assembly of the VVER-1000 reactor.

Article Details

Keywords

MCNP, COBRA-EN, coupling scheme, power distribution

References

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