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Published: 2018-06-30
Abstract Views: 156
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DOI: https://doi.org/10.53747/jnst.v8i2.86
Issue
Vol. 8 No. 2 (2018)
Section
Articles
How to Cite
Tran, Q. D., Nguyen, N. D., Huynh, T. N., Nguyen, K. C. ., & Nguyen, M. T. (2018). Calculation of critical core configurations of a research reactor using MTR, IRT-4M, VVR-KN fuel assemblies. Nuclear Science and Technology, 8(2), 10-18. https://doi.org/10.53747/jnst.v8i2.86

Calculation of critical core configurations of a research reactor using MTR, IRT-4M, VVR-KN fuel assemblies

Tran Quoc Duong1, Nguyen Nhi Dien1, Huynh Ton Nghiem1, Nguyen Kien Cuong 1, Nguyen Minh Tuan1
1 Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat, Vietnam

Main Article Content

Abstract

This paper presents calculation results to determine critical core configurations and a
minimum number of fuel assemblies (FAs) or uranium mass of a research reactor loaded with three types of FAs such as MTR, IRT-4M and VVR-KN. The MCNP5 code and ENDF/B7.1 library were applied to estimate characteristics parameters of the fuel types and the whole core. Infinitive multiplication factor kinf, neutron flux distribution and neutron spectra of the fuels were calculated. The reactor core configurations with three fuel types were modeled in 3-dimensions, and then the effective multiplication factors keff, relative radial power distribution of each configuration were also evaluated. From calculation results, twelve fuel loading schemes were chosen based on lowest uranium mass or smallest number of FAs loaded into the core. In addition, two full core configurations using VVR-KN and MTR FAs and consisting of beryllium reflectors, vertical irradiation facilities, horizontal neutron beam ports, etc. have been proposed for further consideration in thermal hydraulic calculations and safety analysis.

Article Details

Keywords

Research Reactor, MTR, VVR-KN, IRT-4M, critical core configuration, beryllium reflector, MCNP5 code

References

[1]. Chul Gyo Seo et al. “Innovative Design Concepts for the KIJANG Research Reactor”, Proceedings of the KNS 2013 Spring Meeting, Korea, 2013.
[2]. Ayman I. Hawari and Young-Ki Kim. “Design and Characteristics of the Jordan Research and Training Reactor”, Joint IGORR 2014 & IAEA Technical Meeting, November 17–21, 2014, Bariloche, Argentina, 2014.
[3]. Mustafa K. Jaradat et al. “JRTR initial criticality calculations and nuclear commissioning tests”, RRFM Meeting, April 19–23, 2015, Bucharest, Romania, 2015.
[4]. F. Arinkin et al. “Safety analysis for LTA irradiation test at the WWR-K Research Reactor”, Proceedings of the RERTR-2010 Meeting, October 10–14, 2010, Lisbon, Portugal, 2010.
[5]. X-5 Monte Carlo Team, “MCNP5 - A General Monte Carlo N-Particle Transport Code”, Version 5, Volume I, II, III, (revised 10/3/05), April 24, 2003.
[6]. Luong Ba Vien et al. “Design analyses for full core conversion of the Dalat nuclear research reactor”, Journal of Nuclear Science and Technology, VAEA, ISSN 1810-5408, Vol. 4, No. 1, pp. 10-25, 2014.
[7]. Nguyen Nhi Dien et al. “Some main results of commissioning of the Dalat research reactor with low enriched fuel”, Journal of Nuclear Science and Technology, VAEA, ISSN 1810-5408, Vol. 4, No. 1, pp. 36-45, 2014.