Numerical analysis of the 2D C5G7 MOX benchmark using PL equations and a nodal collocation method. (April 2018)

• Record Type: Journal Article
• Authors: Capilla, M.T.; Talavera, C.F.; Ginestar, D.; Verdú, G.
• Is Part Of: Annals of nuclear energy. Volume 114(2018)
• Page Start: 32
• Page End: 41
• Publication Date: 2018-04
• Subjects: Multi-dimensional PL equations -- Spherical harmonics method -- Nodal collocation method -- Criticality calculations -- C5G7 MOX benchmark; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2017.12.002
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: The neutron transport equation is solved with a spherical harmonics-nodal collocation method. The method is applied to the complex reactor seven group 2D NEA C5G7 MOX problem. Results are consistent with the reference Monte Carlo solution. First subcritical models are also computed for full reactor configuration. Abstract: A classical discretization for the angular dependence of the neutron transport equation is based on a truncated spherical harmonics expansion. The resulting system of equations are the P L equations. We review the multi-dimensional P L equations, for arbitrary odd order L, and then we proceed to the spatial discretization of these equations, for rectangular geometries, using a nodal collocation method based on the expansion of the spatial dependence of the fields in terms of orthonormal Legendre polynomials. The validity of the method to deal with complex reactor problems is then studied with the seven-group 2D NEA C5G7 MOX fuel assembly benchmark problem. The solution is computed for different spatial meshes, showing that the P L results are consistent with the reference Monte Carlo solution. Additionally, the first subcritical modes are also computed for the full reactor configuration.