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Modelling of nuclear reactor multi-physics[electronic resource] :from local balance equations to macroscopic models in neutronics and thermal-hydraulics /

紀錄類型:	書目-電子資源 : Monograph/item
杜威分類號:	539.76
書名/作者:	Modelling of nuclear reactor multi-physics : from local balance equations to macroscopic models in neutronics and thermal-hydraulics // Christophe Demazière.
作者:	Demazière, Christophe.
出版者:	London ; : Academic Press,, 2020.
面頁冊數:	1 online resource
標題:	Nuclear reactors.
標題:	Nuclear reactors - Mathematical models.
ISBN:	012815070X (electronic bk.)
ISBN:	9780128150702 (electronic bk.)
ISBN:	0128150696
ISBN:	9780128150696
書目註:	Includes bibliographical references and index.
內容註:	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.
摘要、提要註:	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). --
電子資源:	https://www.sciencedirect.com/science/book/9780128150696

Modelling of nuclear reactor multi-physics[electronic resource] :from local balance equations to macroscopic models in neutronics and thermal-hydraulics /
Demazière, Christophe.

Modelling of nuclear reactor multi-physicsfrom local balance equations to macroscopic models in neutronics and thermal-hydraulics /[electronic resource] :Christophe Demazière. - London ;Academic Press,2020. - 1 online resource

Includes bibliographical references and index.

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.

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). --

ISBN: 012815070X (electronic bk.)Subjects--Topical Terms:

343153
Nuclear reactors.
Index Terms--Genre/Form:

336502
Electronic books.

LC Class. No.: TK9202 / .D45 2020

Dewey Class. No.: 539.76

Modelling of nuclear reactor multi-physics[electronic resource] :from local balance equations to macroscopic models in neutronics and thermal-hydraulics /
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520 $a 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). -- $c Provided by publisher.
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