Screen LibraryModelling of nuclear reactor multi-physics : from local balance equations to macroscopic models in neutronics and thermal-hydraulics /
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...
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| Main Authors: | |
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| Corporate Authors: | |
| Published: |
Academic Press,
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| Publisher Address: | London ; Cambridge, MA : |
| Publication Dates: | [2020] |
| Literature type: | eBook |
| Language: | English |
| Subjects: | |
| Online Access: |
https://www.sciencedirect.com/science/book/9780128150696 |
| Summary: |
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). -- |
| Carrier Form: | 1 online resource (353 pages) |
| Bibliography: | Includes bibliographical references and index. |
| ISBN: |
012815070X 9780128150702 |
| Index Number: | TK9202 |
| CLC: | TL1 |
| Contents: | Introduction -- Transport phenomena in nuclear reactors -- Neutron transport calculations at the cell and assembly levels -- Neutron transport calculations at the core level -- One-/two-phase flow transport and heat transfer -- Neutronic/thermal-hydraulic coupling -- Conclusions. |