The dispersion fuel is with the advantages of high burnup, strong ability of containing fission products and good thermal conductivity. It is widely used as an advanced fuel element in new types of nuclear reactors. However, the dispersion fuel element in which the fuel particles statistically distributed in the matrix material presents some new challenges for the conventional neutron transport simulation methods. In this paper, the Monte Carlo neutron transport simulation method based on the chord length sampling is developed. The method can r...
