Transport Theory and Statistical Physics · 1996 · 16 citations · 10 references
EngineeringNuclear EngineeringComputational GeometryComputational MechanicsComputational PhysicsConvergence AnalysisDiscrete Ordinates MethodEigenvalue ProblemsMultigroup Transport TheoryNumerical AlgorithmsNumerical AnalysisBoundary Condition TreatmentEigenvalue Neutron Transport ProblemsReflector EffectsReflector PhysicsTransport TheoryTruncationTruncation ErrorTruncation Error Analysis
Abstract A new numerical nodal method is developed for multigroup slab-geometry discrete ordinates (SN) eigenvalue problems with no spatial truncation error. The numerical results are exactly those of the dominant analytical solution of the multigroup SN eigenvalue problem on the grid points apart from finite arithmetic considerations and regardless of the spatial grid. We have implemented the option of using the multigroup albedo boundary condition, that is a measure of the reflective power of the neutron reflector, e.g., water or graphite. The Power method used in the outer iterations for convergence of the dominant numerical solution has been accelerated by a scheme based on Tchebycheff extrapolation of the fission source. Numerical results are given to illustrate the method's accuracy.
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Computational methods of neutron transport
M.M.R. Williams · Annals of Nuclear Energy · 1985 · 847 citations
Advances in nuclear science and technology
Journal of the Franklin Institute · 1963 · 158 citations
R. V. Meghreblian · Nuclear Science and Engineering · 1961 · 94 citations