Compartir
Modelling of Nuclear Reactor Multi-Physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics (en Inglés)
Christophe DemaziÈRe (Autor)
·
Academic Press
· Tapa Blanda
Modelling of Nuclear Reactor Multi-Physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics (en Inglés) - Christophe DemaziÈRe
Elige la lista en la que quieres agregar tu producto o crea una nueva lista
✓ Producto agregado correctamente a la lista de deseos.
Ir a Mis Listas
Origen: Estados Unidos
(Costos de importación incluídos en el precio)
Se enviará desde nuestra bodega entre el
Lunes 24 de Junio y el
Lunes 08 de Julio.
Lo recibirás en cualquier lugar de Argentina entre 1 y 3 días hábiles luego del envío.
Reseña del libro "Modelling of Nuclear Reactor Multi-Physics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics (en Inglés)"
Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations. The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer). The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly lev
- 0% (0)
- 0% (0)
- 0% (0)
- 0% (0)
- 0% (0)
Todos los libros de nuestro catálogo son Originales.
El libro está escrito en Inglés.
La encuadernación de esta edición es Tapa Blanda.
✓ Producto agregado correctamente al carro, Ir a Pagar.
