[en] Variational principles which employ discontinuous shape functions for the angular and/or the spatial component of the neutron flux are established to obtain numerical solutions for neutron diffusion and transport equations. Implementing discontinuous finite element methods reduces the total nodal unknowns and hence the over all computational efforts. This reduction varies from one problem to another. In this paper one group neutron transport problems are solved by varying only the order of spherical harmonic expansion for the angular component of the flux. A comparison of the solutions obtained from the discontinuous approach with either a published solutions or a conventional finite element solutions shows that the method is a very effective tool for reactor calculations