Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

Author:

Dwijayanto R. Andika Putra1,Ardiansyah Harun23,Harto Andang Widi4

Affiliation:

1. Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency , South Tangerang 15314, Indonesia

2. Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois Urbana Champaign , Champaign, IL 61801

3. University of Illinois Urbana-Champaign

4. Department of Nuclear Engineering and Physics Engineering, Faculty of Engineering, Universitas Gadjah Mada , Yogyakarta 55281, Indonesia

Abstract

Abstract Thermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using Monte Carlo N-particle 6.2 (MCNP6.2) and Serpent-2 reactor physics codes with evaluated nuclear data files/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. While the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.

Publisher

ASME International

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