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Published: 2016-06-30
Abstract Views: 267
Views PDF: 47
DOI: https://doi.org/10.53747/jnst.v6i2.143
Issue
Vol. 6 No. 2 (2016)
Section
Articles
How to Cite
Nguyen, H. T., Tran, V. P., Nguyen, T. K., Tran, V. T., & Nguyen , M. T. (2016). Representative neutronic characteristics calculations for the VVER-1000 reactors using SRAC and MCNP5. Nuclear Science and Technology, 6(2), 21-30. https://doi.org/10.53747/jnst.v6i2.143

Representative neutronic characteristics calculations for the VVER-1000 reactors using SRAC and MCNP5

Nguyen Huu Tiep1, Tran Viet Phu1, Nguyen Tuan Khai1, Tran Vinh Thanh1, Nguyen Minh Tuan2
1 Institute for Nuclear Science and Technology 179 - Hoang Quoc Viet, Nghia Do, Cau Giay, Hanoi, Vietnam
2 Nuclear Research Institute 01 – Nguyen Tu Luc, Da Lat, Lam Dong, Viet Nam

Main Article Content

Abstract

This paper presents the results of neutronic calculations using the deterministic and Monte-Carlo methods (the SRAC and MCNP5codes) for the VVER MOX Core Computational Benchmark Specification and the VVER-1000/V392 reactor core. The power distribution and keff value have been calculated for a benchmark problem of VVER core. The results show a good agreement between the SRAC and MCNP5 calculations. Then, neutronic characteristics of VVER-1000/V392 such as power distribution, infinite multiplication factor (k-inf) of the fuel assemblies, effective multiplication factor keff, peaking factor and Doppler coefficient were calculated using the two codes.

Article Details

Keywords

VVER-1000/V392, SRAC, MCNP5, power distribution, multiplication factor, Doppler coefficient

References

[1] VVER-1000 MOX core Computational Benchmark, Specification and Results, Expert Group on Reactor - based Plutonium Disposition, Eugeny Gomin, Mikhail Kalugin, Dmitry Oleynik Russian Research Centre, Kurchatov Institute, NEA No 6088, © OECD, 2006
[2] VVER-1000 MOX core computational Benchmark analysis using indigenous codes EXCEL, TRIHEX-FA and HEXPIN, Thilagam, L., Jagannathan, V., Sunil Sunny, C., Subbaiah, K.V.,. Ann. Nucl. Energy 36, 1502-1515, 2009
[3] Inter-comparison of JEF-2.2 and JEFF-3.1 evaluated nuclear data through Monte Carlo analysis of VVER-1000 MOX core computational Benchmark, Thilagam, L., Karthikeyan, R., Jagannathan, V., Subbaiah, K.V., Lee, S.M., Ann. Nucl. Energy 37, 144 -165, 2010.
[4]Application of CNUREAS and MCNP5 codes to VVER-1000 MOX Core Computational Benchmark – Senem SentürkLüle, Levent Ozdemir, Adem Erdogan, Turkish Atomic Energy Authority, Cekmece Nuclear Research and Training Center, Kucukcekmece, 34303, Istanbul, Turkey- Progress in Nuclear Energy 85454 – 461, 2015
[5] Risk Engineering LTD (2012) INTRODUCTION TO VVER TECHNOLOGIES. Training course provided for Vietnam Atomic Energy Institute VINATOM, Sofia, Bulgaria, 15 Jan – 9 March 2012.
[6] Doppler coefficient of reactivity ― benchmark calculations for different enrichments of UO2, Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007), L. Thilagam, C. Sunil Sunny and K.V. Subbaiah; K. Devan; Lee, Young-Seok; V. Jagannathan. April 15-19, 2007.
[7] Doe fundamentals handbook nuclear physics and reactor theory, U.S. Department of Energy, Washington, D.C. 20585, Jan 1993.