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Development of galerkin finite element method three-dimensional computational code for the multigroup neutron diffusion equation with unstructured tetrahedron elements

Hosseini, S. A ; Sharif University of Technology

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  1. Type of Document: Article
  2. DOI: 10.1016/j.net.2015.10.009
  3. Publisher: Korean Nuclear Society
  4. Abstract:
  5. In the present paper, development of the three-dimensional (3D) computational code based on Galerkin finite element method (GFEM) for solving the multigroup forward/adjoint diffusion equation in both rectangular and hexagonal geometries is reported. Linear approximation of shape functions in the GFEM with unstructured tetrahedron elements is used in the calculation. Both criticality and fixed source calculations may be performed using the developed GFEM-3D computational code. An acceptable level of accuracy at a low computational cost is the main advantage of applying the unstructured tetrahedron elements. The unstructured tetrahedron elements generated with Gambit software are used in the GFEM-3D computational code through a developed interface. The forward/adjoint multiplication factor, forward/adjoint flux distribution, and power distribution in the reactor core are calculated using the power iteration method. Criticality calculations are benchmarked against the valid solution of the neutron diffusion equation for International Atomic Energy Agency (IAEA)-3D and Water-Water Energetic Reactor (VVER)-1000 reactor cores. In addition, validation of the calculations against the P1 approximation of the transport theory is investigated in relation to the liquid metal fast breeder reactor benchmark problem. The neutron fixed source calculations are benchmarked through a comparison with the results obtained from similar computational codes. Finally, an analysis of the sensitivity of calculations to the number of elements is performed
  6. Keywords:
  7. Finite element method ; Forward/adjoint fluxes ; Galerkin ; Gambit ; Power distribution ; Unstructured tetrahedron elements
  8. Source: Nuclear Engineering and Technology ; Volume 48, Issue 1 , 2016 , Pages 43-54 ; 17385733 (ISSN)
  9. URL: http://www.sciencedirect.com/science/article/pii/S1738573315002211