American National Standard for the Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors PDF Download
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Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 40
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Book Description
Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 40
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Book Description
Author: Mihály Makai
Publisher: Springer
ISBN: 3319545760
Category : Technology & Engineering
Languages : en
Pages : 438
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Book Description
This book presents a comprehensive overview of the computerized core monitoring techniques currently employed at pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power plants. It also offers a brief overview of the corresponding techniques at research and materials testing reactors. The book combines detailed descriptions of the theoretical background and fundamental underlying principles as well as the practical applications of core surveillance. It not only provides numerous industrial examples to illustrate how complex computerized systems are able to support the safe operation of nuclear reactors, but also outlines some new application areas that were made possible only by state-of-the-art computing resources. Thanks to its practical approach, it serves as a valuable and practical reference book for readers interested in the surveillance of nuclear reactors, ranging from undergraduate and postgraduate students to researchers and experts working at research reactors and nuclear power plants, as well as at nuclear regulatory authorities.
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 936
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Book Description
Author: Doug Reilly
Publisher:
ISBN: 9780160327247
Category : Non-destructive testing
Languages : en
Pages : 700
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Book Description
Author: Christophe Demazière
Publisher: Academic Press
ISBN: 012815070X
Category : Technology & Engineering
Languages : en
Pages : 370
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Book Description
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 levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. - Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference - Analyses the emerging area of multi-physics and multi-scale reactor modelling - Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
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Book Description
Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 808
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Book Description
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 852
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 722
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Book Description
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1224
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Book Description
