  The neutronic properties of Molten Salt Reactor are different from that of
traditional solid-fuel reactors due to its nuclear fuel particularity. Based
upon MCNP code, the influence of the size and shape of fuel salt channel on
neutron physics of MSR cell was studied systematically in this work. The
results show that the infinite multiplication factors increases first and then
decreases with the change of graphite cell size under the condition of given
fuel 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 different
fuel salt channel shapes are in good agreement; when the average chord length
is relatively large, the k values with different fuel salt channel shapes are
greatly different. In addition, some examples of practical application of this
work are illustrated in the end, including cell selection for the core and
thermal expansion displacement analysis of the cell.
