Academic Journal
SN Method for Solving Transport Source Problems With Anisotropic Scattering.
| Τίτλος: | S |
|---|---|
| Συγγραφείς: | Morató, S., Miró, R., Bernal, Á., Roman, J. E., Verdú, G., Habib, Mohammad Rezwan |
| Πηγή: | Science & Technology of Nuclear Installations; 7/19/2026, Vol. 2026, p1-11, 11p |
| Θεματικοί όροι: | Neutron transport theory, Neutron scattering, Software libraries (Computer programming), Finite difference method, Neutron temperature, Sparse matrices |
| Περίληψη: | A discrete ordinates (SN) method has been applied to the solution of the steady‐state multigroup neutron transport equation in Cartesian geometry. Angular and spatial discretization were performed using the (SN) scheme and the finite difference method, respectively, with isotropic and anisotropic scattering treated up to arbitrary order. The algorithms were implemented in a FORTRAN code named n‐DOTEC. The contribution of this work lies in the development and verification of a computational framework for one‐ and two‐dimensional fixed‐source transport problems, capable of handling multiple energy groups and anisotropic scattering expansions of arbitrary order, and using PETSc together with MUMPS for the solution of the resulting sparse linear systems. In the two‐dimensional case, the code includes a product quadrature (PQ) developed by the authors, based on Gauss‐Legendre quadrature for both polar and azimuthal angles, with point weights defined as the product of the corresponding one‐dimensional weights. The code was validated against several one‐dimensional benchmarks and a two‐dimensional benchmark problem. Test cases include fixed‐source problems with vacuum and reflective boundary conditions under demanding configurations that require high‐order (SN) to achieve accuracy. The numerical results demonstrate good agreement with analytical solutions and reference codes such as DANTSYS and PARTISN. Reported mean relative errors were below 1% for most cases, and as low as 0.0005% for a two‐group anisotropic scattering benchmark, confirming the robustness of the implementation. The method efficiently computes flux distributions for any number of energy groups, and its simple formulation makes it a reliable tool for transport calculations. In addition, n‐DOTEC has potential applications in generating variance‐reduction parameters, such as weight windows, for Monte Carlo simulations. [ABSTRACT FROM AUTHOR] |
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| Βάση Δεδομένων: | Complementary Index |
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