A discontinuous Bubnov-Galerkin spectral element spatial discretisation of the first-order form of the neutron transport equation using a discrete ordinate angular discretisation with multidimensional anisotropic dispersion and dissipation analysis
Fields of Study & Subjects
Nuclear reactor physics and engineering
Advanced Numerical Methods in Computational Mathematics
Differential Equations and Boundary Problems
Publication details
- Journal / source
- Annals of Nuclear Energy
- Publisher
- Elsevier BV
- Volume
- 239
- Pages
- 112630–112630
- Publication date
- 24 July 2026
- Language
- EN