Abstract
The method of characteristics (MOC) technique has been widely used to solve the neutron transport equation in reactor fuel lattice calculations because of its high adaptability for unstructured meshes. This chapter introduces the derivation and solution of the MOC equation. A detailed derivation of MOC solution is introduced first. Some important approximations essential to the accuracy of MOC during the derivation are explained. Then the algorithms of 2D and 3D MOC solvers are described. Afterward, a practical 2D/1D fusion algorithm, which has been widely used for assembly and whole-core heterogeneous calculations, is introduced. Finally, some numerical results are provided to show the performance of different solvers.
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