Deterministic Numerical Methods for Unstructured-Mesh Neutron Transport Calculation: Woodhead Publishing Series in Energy
Editat de Liangzhi Cao, Hongchun Wuen Limba Engleză Paperback – 28 aug 2020
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.
- Combines the theoretical models with numerical methods and results in one complete resource
- Presents the latest progress on the topic in an easy-to-navigate format
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Specificații
ISBN-13: 9780128182215
ISBN-10: 0128182210
Pagini: 288
Ilustrații: 90 illustrations (40 in full color)
Dimensiuni: 152 x 229 x 20 mm
Greutate: 0.4 kg
Editura: ELSEVIER SCIENCE
Seria Woodhead Publishing Series in Energy
ISBN-10: 0128182210
Pagini: 288
Ilustrații: 90 illustrations (40 in full color)
Dimensiuni: 152 x 229 x 20 mm
Greutate: 0.4 kg
Editura: ELSEVIER SCIENCE
Seria Woodhead Publishing Series in Energy
Public țintă
Graduate students in nuclear engineering and nuclear technology applications; nuclear engineers and scientists working on advanced systems aiming to keep abreast of the latest research; professors and students of advanced courses in the nuclear fieldCuprins
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