Abstract
It is found that the even-parity form of the neutron transport equation is well suited to a variational formulation in conjunction with the finite element approximation. A finite element technique is studied in the context of reactor physics calculations which is of particular interest in the nuclear engineering field. Multi-region slab problems for a given source distribution and critical slab problems are solved with an accuracy as good as the best problem techniques available. An exact solution is obtained for the special case of forward scattering with uniform source distribution in a slab reactor.
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