Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation

Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation presents the latest deterministic numerical methods for neutron transport equations (NTEs) with complex geometry, which are of great demand in recent years due to the rapid development of advanced nuclear reactor concepts and high-performance computational technologies. This book covers the wellknown methods proposed and used in recent years, not only theoretical modeling but also numerical results.

This book provides readers with a very thorough understanding of unstructured neutron transport calculations and enables them to develop their own computational codes. The fundamentals, numerical discretization methods, algorithms, and numerical results are discussed. Researchers and engineers from utilities and research institutes are provided with examples on how to model an advanced nuclear reactor, which they can then apply to their own research projects and lab settings.

1. Neutron transport equation 2. Collision probability method 3. Transmission probability method for triangular meshes 4. Current-coupled collision probability method 5. The method of characteristics 6. PN-FEM method 7. The discrete ordinate method 8. Mesh-free method 9. Other methods