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Published: 2019-09-15
Abstract Views: 276
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DOI: https://doi.org/10.53747/jnst.v9i3.41
Issue
Vol. 9 No. 3 (2019)
Section
Articles
How to Cite
Nguyen Kien, C., Nguyen Thi , D., Tran Viet, P., Nguyen Huu, T., & Pham Nhu Viet, H. (2019). Modeling of the Dalat Nuclear Research Reactor (DNRR) with the Serpent 2 Monte Carlo code. Nuclear Science and Technology, 9(3), 21-29. https://doi.org/10.53747/jnst.v9i3.41

Modeling of the Dalat Nuclear Research Reactor (DNRR) with the Serpent 2 Monte Carlo code

Nguyen Kien Cuong1, Nguyen Thi Dung2, Tran Viet Phu2, Nguyen Huu Tiep2, Pham Nhu Viet Ha2
1 Nuclear Research Institute (NRI), Vietnam Atomic Energy Institute (VINATOM), 01 Nguyen Tu Luc, Dalat, Lamdong 670000, Viet Nam
2 Institute for Nuclear Science and Technology (INST), Vietnam Atomic Energy Institute (VINATOM), 179 Hoang Quoc Viet str., Cau Giay dist., Hanoi 100000, Viet Nam

Main Article Content

Abstract

This paper presents a model development of the Dalat Nuclear Research Reactor (DNRR) loaded with low enriched uranium (LEU) fuel using the Serpent 2 Monte Carlo code. The purpose is to prepare the DNRR Serpent 2 model for performing fuel burnup calculations of the DNRR as well as for generating multi-group neutron cross sections to be further used in the kinetics calculations of the DNRR with a 3D reactor kinetics code. The DNRR Serpent 2 model was verified through comparing with the MCNP6 criticality calculations under different reactor conditions. The parameters to be compared include the effective neutron multiplication factor, radial and axial power
distributions, and thermal neutron flux distributions. The comparative results generally show a good agreement between Serpent 2 and MCNP6 and thus indicate that the DNRR Serpent 2 model can be used for further calculations of the DNRR.

Article Details

Keywords

DNRR, neutronics, Monte Carlo simulation, Serpent 2, MCNP6

References

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