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The neutronic properties of Molten Salt Reactor are different from that oftraditional solid-fuel reactors due to its nuclear fuel particularity. Basedupon MCNP code, the influence of the size and shape of fuel salt channel onneutron physics of MSR cell was studied systematically in this work. Theresults show that the infinite multiplication factors increases first and thendecreases with the change of graphite cell size under the condition of givenfuel volume fraction. In the case of the same FVF and average chord length,when the average chord length is relatively small, the k values with differentfuel salt channel shapes are in good agreement; when the average chord lengthis relatively large, the k values with different fuel salt channel shapes aregreatly different. In addition, some examples of practical application of thiswork are illustrated in the end, including cell selection for the core andthermal expansion displacement analysis of the cell.

Neutronics Analysis for MSR Cell with Different Fuel Salt Channel Geometry