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

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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.

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References

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