Thermal Engineering of Nuclear Power Stations: Balance-of-Plant Systems, Bowman Charles F., Bowman Seth N.
Название: Closed nuclear fuel cycle with fast reactors ISBN: 0323993087 ISBN-13(EAN): 9780323993081 Издательство: Elsevier Science Рейтинг: Цена: 20920.00 р. 23244.00-10% Наличие на складе: Есть (5 шт.) Описание: Closed Nuclear Fuel Cycle with Fast Reactors: Handbook of Russian Nuclear Power provides unique insights into research and practical activities from leading Russian experts. It presents readers with unprecedented insight and essential knowledge surrounding nuclear fast reactor technologies, as well as novel methods to close the nuclear fuel cycle to achieve cleaner, more environmentally friendly, and more efficient nuclear power. Using the Proryv Project as a framework, the book's contributors provide detailed descriptions of technologies in development in Russia, allowing readers from around the globe to gain a thorough understanding which they can then apply to their own research and practice.
Nuclear engineers and technologists of fast reactors, advanced reactors and fuel cycles will use this book as a guide to inform new technology development. They will be able to use the experiences from the Proryv Project to drive fast reactor development with closed fuel cycles for the future.
Автор: Bowman, Charles F. , Bowman, Seth N. Название: Thermal Engineering of Nuclear Power Stations ISBN: 0367820390 ISBN-13(EAN): 9780367820398 Издательство: Taylor&Francis Рейтинг: Цена: 21437.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: The book serves as a ready reference to better analyze common engineering challenges in the areas of turbine cycle analysis, thermodynamics, and heat transfer. It covers mechanical aspects of the entire nuclear station balance-of-plant from the source of the motive steam to the discharge and/or utilization of waste heat and beyond.
Автор: Demaziere, Christophe Название: Modelling Of Nuclear Reactor Multi-Physics ISBN: 0128150696 ISBN-13(EAN): 9780128150696 Издательство: Elsevier Science Рейтинг: Цена: 23749.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
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.
Автор: Wang, Jun Название: Nuclear Power Plant Design And Analysis Codes ISBN: 0128181907 ISBN-13(EAN): 9780128181904 Издательство: Elsevier Science Рейтинг: Цена: 31160.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li, Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.
Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs.
Автор: Saha Pradip Название: Nuclear Reactor Thermal-Hydraulics: Past, Present and Future ISBN: 0791861287 ISBN-13(EAN): 9780791861288 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16632.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Summarizes the major developments on nuclear reactor thermal-hydraulics over the last fifty years, primarily for water-cooled reactors, and provides a direction for the future thermal-hydraulic developments for water-cooled, including small modular reactors or SMR, and Generation IV reactors.
Автор: Koizumi, Yasuo Название: Fundamentals Of Thermal And Nuclear Power Generation ISBN: 0128207337 ISBN-13(EAN): 9780128207338 Издательство: Elsevier Science Рейтинг: Цена: 26107.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Fundamentals of Thermal and Nuclear Power Generation is the first volume in the JSME Series in Thermal and Nuclear Power Generation. The first part of this volume provides a thorough and complete reference on the history of thermal and nuclear power generation, which has informed and sculpted today's industry. It prepares readers for subsequent publications in the series that address more advanced topics and will particularly benefit early career researchers and those approaching the industry from an alternative discipline.
Modern thermal and nuclear power generation systems and technologies are then explored, including clear analysis on the fundamentals of thermodynamics, hydrodynamics, thermal engineering, combustion engineering, and nuclear physics. The impact of these technologies on society is considered throughout, as well as supply issues, accident risk analysis, and important emission and sustainability considerations.
This book is an invaluable resource for researchers and professional engineers in nuclear and thermal energy engineering, and postgraduate and undergraduate students in power generation, especially nuclear and thermal.
Автор: Ozawa, Mamoru Название: Advances In Power Boilers ISBN: 0128203609 ISBN-13(EAN): 9780128203606 Издательство: Elsevier Science Рейтинг: Цена: 26107.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Advances in Power Boilers is the second volume in the JSME Series on Thermal and Nuclear Power Generation. The volume provides the fundamentals of thermal power generation by firstly analysing different fuel options for thermal power generation and then also by tracing the development process of power boilers in about 300 years. The design principles and methodologies as well as the construction, operation and control of power boilers are explained in detail together with practical data making this a valuable guide for post-graduate students, researchers, engineers and regulators developing knowledge and skill of thermal power generation systems.
Combining their wealth of experience and knowledge, the author team presents recent advanced technologies to the reader to enable them to further research and development in various systems, notably combined cycles, USC and A-USC, as well as PFBC and IGCC. The most recent best practices for material development for advanced power system as well as future scope of this important field of technology are clearly presented, and environment, maintenance, regulations and standards are considered throughout. The inclusion of photographs and drawings make this a unique reference for all those working and researching in the thermal engineering fields.
The book is directed to professional engineers, researchers and post-graduate students of thermal engineering in industrial and academic field, as well as plant operators and regulators.
Автор: Maksym Maksymov, Oleksandr Brunetkin, Svitlana Alyokhina Название: Thermal and Reliability Criteria for Nuclear Fuel Safety ISBN: 8770224013 ISBN-13(EAN): 9788770224017 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 13167.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience. The book starts by looking at the physical safety basis of water-water energetic reactor (WWER) nuclear fuel. It goes on to discuss modern approaches to the heat exchange modelling in nuclear power plant equipment. Next, the safety criteria when making a decision about dry storage for WWER-1000 fuel assembly are discussed. Then the effect of reactor capacity cyclic changes on energy accumulation of creep formations in fuel cladding is covered in full, along with a chapter on the analysis of WWER-1000 fuel cladding failure. Finally, the book finishes with a description of thermal safety criteria for dry storage of spent nuclear fuel.
The book is essential reading for anyone concerned with NPP maintenance and safety.
Автор: Takeda Tetsuaki, Inagaki Yoshiyuki Название: High Temperature Gas-Cooled Reactors ISBN: 0128210311 ISBN-13(EAN): 9780128210314 Издательство: Elsevier Science Рейтинг: Цена: 26107.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
High-Temperature Gas Reactors is the fifth volume in the JSME Series on Thermal and Nuclear Power Generation. Series Editor Yasuo Koizumi and his Volume editors Tetsuaki Takeda and Yoshiyuki Inagaki present the latest research on High-Temperature Gas Reactor (HTGR) development and utilization, beginning with an analysis of the history of HTGRs. A detailed analysis of HTGR design features, including reactor core design, cooling tower design, pressure vessel design, I&C factors and safety design, provides readers with a solid understanding of how to develop efficient and safe HTGR within a nuclear power plant.
The authors combine their knowledge to present a guide on the safety of HTGRs throughout the entire reactor system, drawing on their unique experience to pass on lessons learned and best practices to support professionals and researchers in their design and operation of these advanced reactor types. Case studies of critical testing carried out by the authors provide the reader with firsthand information on how to conduct tests safely and effectively and an understanding of which responses are required in unexpected incidents to achieve their research objectives. An analysis of technologies and systems in development and testing stages offer the reader a look to the future of HTGRs and help to direct and inform their further research in heat transfer, fluid-dynamics, fuel options and advanced reactor facility selection.
This volume is of interest for nuclear and thermal energy engineers and researchers focusing on HTGRs, HTGR plant designers and operators, regulators, post graduate students of nuclear engineering, national labs, government officials and agencies in power and energy policy and regulations.
Автор: Riznic, Jovica Название: Pressurized Heavy Water Reactors,7 ISBN: 0128220546 ISBN-13(EAN): 9780128220542 Издательство: Elsevier Science Рейтинг: Цена: 26444.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs.
Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties.
Автор: Riznic, Jovica Название: Pressurized Heavy Water Reactors,8 ISBN: 032385382X ISBN-13(EAN): 9780323853828 Издательство: Elsevier Science Рейтинг: Цена: 26444.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:
Pressurized Heavy Water Reactors: Atucha-II, the eighth volume in the JSME Series on Thermal and Nuclear Power Generation, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components, and the role of codes in PHWR and Nuclear Regulation and Licensing. Including contemporary capabilities and challenges of nuclear technology, the book offers solutions and advice on common problems faced, guiding the reader through safe and approved processes that will help them reach suitable solutions.
Professionals involved in lifecycle assessments and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing.
Автор: Morishita, Masaki Название: Sodium-Cooled Fast Reactors,3 ISBN: 0128240768 ISBN-13(EAN): 9780128240762 Издательство: Elsevier Science Рейтинг: Цена: 26107.00 р. Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Now the most wanted person in Sonande, her only hope of reclaiming what is rightfully hers lies in a divine power hidden in the long-lost city of her ancestors. Meanwhile, the resurrection of Karina`s sister has spiraled the world into chaos, with disaster after disaster threatening the hard-won peace Malik has found as Farid`s apprentice.
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