Verification and Geometry Optimization of a One Fluid Molten Salt Reactor (OFMSR) with Fixed Volume
Published in ASME Journal of Nuclear Engineering and Radiation Science, 2024
Various OFMSR core configurations with fixed volume have been studied using MCNP6.2 and Serpent-2 codes. It was apparent that radial blanket configuration generally showed a better neutronic performance than axial blanket configuration. Radial-1 possesses the better of the two radial configurations, with strongest negative TCR, longer Λ, and highest BR. In spite of marginally larger fuel inventory than its axial counterpart, Radial-1 still has the shortest DT. To obtain more optimized neutronic performance with fixed fuel salt volume, OFMSR is better using radial blanket configuration. Therefore, Radial-1 configuration is deemed as the neutronically optimum design among the models simulated in this study, and will be used for future design optimization.
Recommended citation: R. A. P. Dwijayanto, H. Ardiansyah, and A. W. Harto, “Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume,” Journal of Nuclear Engineering and Radiation Science, vol. 10, no. 3, p. 031301, July 2024, doi: 10.1115/1.4064465.
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