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Published: 2017-12-30
Abstract Views: 139
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DOI: https://doi.org/10.53747/jnst.v7i4.92
Issue
Vol. 7 No. 4 (2017)
Section
Articles
How to Cite
Bui, P. N., Huynh, T. N., Nguyen, N. D., & Le, V. V. (2017). Calculation of neutronic characteristics in different reflector materials with a 15-MWt reactor core using VVR-KN fuel type. Nuclear Science and Technology, 7(4), 9-15. https://doi.org/10.53747/jnst.v7i4.92

Calculation of neutronic characteristics in different reflector materials with a 15-MWt reactor core using VVR-KN fuel type

Bui Phuong Nam1, Huynh Ton Nghiem1, Nguyen Nhi Dien1, Le Vinh Vinh1
1 Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat, Viet Nam

Main Article Content

Abstract

VVR-KN is one of the low enriched fuel types intended for a research reactor of a new Centre for Nuclear Energy Science and Technology (CNEST) of Viet Nam. As a part of design orientation for the new research reactor, the calculations of neutronic characteristics in a reactor core reflector using different materials were carried out. The investigated core configuration is a 15-MWt power loaded with VVR-KN fuel assemblies and surrounded by a reflector using beryllium, heavy water or graphite respectively. MCNP5 code together with up-to-date nuclear data libraries were used for these calculations. This paper presents the calculation results of neutron energy spectrum, neutron spatial distribution in the reflector using the above-mentioned materials. Besides, neutronic characteristics calculated for silicon doping irradiation holes in the reflector are also presented and the utilization capabilities of different reflector materials are discussed.

Article Details

Keywords

VVR-KN fuel, MCNP5, reflector materials, silicon doping irradiation hole

References

[1] National research project “Study on calculation of neutronic characteristics, thermo-hydraulics and safety analysis of a new research reactor proposed by the Russian Federation for the Centre for Nuclear Energy Science and Technology of Viet Nam”, ĐTĐL-CN.50/15, Ha Noi, 2016.
[2] F. Arinkin, et al., “Results of the Trial of Lead Test Assemblies in the WWR-K Reactor”, RRFM Conference, Slovenia, 2014.
[3] A. A. Shaimerdenov, et al., “Physical and Power Start-up of WWR-K Research Reactor with LEU Fuel”, RERTR Intenational Meeting, Belgium, 2016.
[4] Forrest B. Brown, et al., “MCNP – A General Monte-Carlo N-Particle Transport Code Version 5”, LA-UR-03-1987, Los Alamos National Laboratory, 2008.
[5] Nguyen Nhi Dien et al., “Some main results of commissioning of the Dalat research reactor with low enriched fuel”, Nuclear Science and Technology, Vol. 4, No. 1 (2014), pp. 35-45.
[6] A. C. Kahler, et al., “The NJOY Nuclear Data Processing System”, LA-UR-12-27079, Los Alamos National Laboratory, 2012.
[7] “Utilization Related Design Features of Research Reactors: A Compendium”, Technical Reports Series No. 455, IAEA, Vienna, 2007.
[8] “Neutron Transmutation Doping of Silicon at Research Reactors”, IAEA-TECDOC-1681, Vienna, 2012.
[9] Hak-Sung Kim et al., “Design of a Neutron Screen for 6-inch Neutron Transmutation Doping in HANARO”, Nuclear Engineering and Technology, Vol. 38, No. 7, 2006.