Numerical analysis of the 2D C5G7 MOX benchmark using PL equations and a nodal collocation method
- 1. Departamento de Matemática Aplicada, Universitat Politècnica de València, Camino de Vera 14, E-46022 Valencia (Spain)
- 2. Departamento de Ingeniería Química y Nuclear, Universitat Politècnica de València, Camino de Vera 14, E-46022 Valencia (Spain)
Description
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 PL equations. We review the multi-dimensional PL 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 PL results are consistent with the reference Monte Carlo solution. Additionally, the first subcritical modes are also computed for the full reactor configuration.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.12.002Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.12.002;
- PII
- S0306454917304553;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 114
- Journal Page Range
- p. 32-41
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50079349
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; FUEL ASSEMBLIES; LEGENDRE POLYNOMIALS; MIXED OXIDE FUELS; MONTE CARLO METHOD; NEA; NEUTRON TRANSPORT THEORY; NUMERICAL ANALYSIS; SPHERICAL CONFIGURATION
- Descriptors DEC
- CALCULATION METHODS; CONFIGURATION; ENERGY SOURCES; FUELS; FUNCTIONS; INTERNATIONAL ORGANIZATIONS; MATERIALS; MATHEMATICS; NUCLEAR FUELS; OECD; POLYNOMIALS; REACTOR MATERIALS; SOLID FUELS; TRANSPORT THEORY
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.