engleski

PARTISN5.97 Code Verification Using keff Analytical Benchmarks

This paper presents verification of the PARTISN5.97 code for several one-dimensional benchmark problems with analytic keff eigenvalue and eigenfunction solutions to the neutron transport equation in several geometries. Verification checks that the implemented code precisely reflects the intended calculations and that these calculations have been executed correctly, while validation would improve the accuracy of these calculated results usually with experimental data. The motivation for this analysis was in verification of the PARTISN5.97 transport theory algorithms when applied to keff calculation of the slab, cylindrical, and spherical geometries with one-media and one- energy group, including anisotropic scattering. The infinite slab with finite thickness problem was also extended to two-energy group problem using anisotropic P1 scattering matrix. The selected benchmarks were chosen to cover problems with simple geometry, few energy groups, and simplified (linearly anisotropic) scattering models, for which analytical solution exists. The macroscopic neutron cross sections, giving reasonable representation of materials used, were extracted from the literature so they are not general-purpose cross sections for predicting criticality experiments, but are rather used to verify algorithm performance. Various characteristics of deterministic code numerics can also be investigated using these benchmark problems, e.g. space and angle discretization, Legendre expansion order, convergence acceleration techniques, and so on. For that purpose, we have used PARTISN5.97 code package, which is a modular computer program designed to solve the time-independent or dependent multigroup discrete ordinates (SN) form of the Boltzmann transport equation in several different geometries. The SN form of approximation is used for treating the angular dependence of the particle distribution, while several spatial differencing options use computational mesh which may consist of either a standard orthogonal mesh or a block adaptive orthogonal mesh. Both inner and outer iterations can be accelerated using the diffusion or transport synthetic acceleration methods. The obtained PARTISN5.97 eigenvalue results showed a good agreement with the referenced analytical benchmark test set.

PARTISN5.97, criticality, eigenvalue, neutron transport, analytical benchmark

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