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Science and Technology of Nuclear Installations
Volume 2017, Article ID 2615409, 10 pages
https://doi.org/10.1155/2017/2615409
Research Article

Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5

1Faculty of Applied Sciences, Ton Duc Thang University, Ho Chi Minh City 700000, Vietnam
2Institute of Fundamental and Applied Sciences, Duy Tan University, 3 Quang Trung, Da Nang 550000, Vietnam
3Nuclear Research Institute, VINATOM, 01 Nguyen Tu Luc, Dalat, Lamdong 670000, Vietnam
4Institute for Nuclear Science and Technology, VINATOM, 179 Hoang Quoc Viet, Hanoi 100000, Vietnam
5Western University Hanoi, Yen Nghia Ward, Ha Dong District, Hanoi 100000, Vietnam

Correspondence should be addressed to Giang Phan; nv.ude.tdt@gnaignahp and Hoai-Nam Tran; nv.ude.utd@4maniaohnart

Received 7 June 2017; Revised 25 August 2017; Accepted 24 September 2017; Published 27 December 2017

Academic Editor: Arkady Serikov

Copyright © 2017 Giang Phan et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Abstract

Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system. The effective multiplication factors, keff, were analyzed for the core at criticality conditions and in two cases corresponding to the complete withdrawal and the full insertion of control rods. MCNP5 calculations were also conducted and compared to that obtained with the SRAC code. The results show that the difference of the keff values between the codes is within 55 pcm. Compared to the criticality conditions established in the experiments, the maximum differences of the keff values obtained from the SRAC and MCNP5 calculations are 119 pcm and 64 pcm, respectively. The radial and axial power peaking factors are 1.334 and 1.710, respectively, in the case of no control rod insertion. At the criticality condition these values become 1.445 and 1.832 when the control rods are partially inserted. Compared to MCNP5 calculations, the deviation of the relative power densities is less than 4% at the fuel bundles in the middle of the core, while the maximum deviation is about 7% appearing at some peripheral bundles. This agreement indicates the verification of the analysis models.