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Discontinuous Finite Element Method for Solving the Two-Dimesional Neutron Transport Equation on Lagrangian Meshes

G. Samba

Nuclear Science and Engineering / Volume 92 / Number 2 / Pages 197-203

February 1986

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It is often desirable to solve the two-dimensional multigroup transport equation for (r-z) geometries directly given by hydrodynamic calculations. Usually, only Monte Carlo codes can compute α or k eigenvalues on such geometries. Most deterministic codes use an orthogonal mesh or restrict the mesh to a regular triangular grid. Other methods were developed at Commissariat à l'Energie Atomique and Los Alamos National Laboratory but do not solve the problem of sliding between two Lagrangian blocks. Thus, a production code has been developed that solves these problems and is able to obtain α or k eigenvalues with a good degree of accuracy for such geometries.

 
 
 
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