Контакты/Проезд  Доставка и Оплата Помощь/Возврат
История
  +7 707 857-29-98
  +7(7172) 65-23-70
  10:00-18:00 пн-пт
  shop@logobook.kz
   
    Поиск книг                        
Найти
  Зарубежные издательства Российские издательства  
Авторы | Каталог книг | Издательства | Новинки | Учебная литература | Акции | Бестселлеры | |
 

Nuclear Reactor Technology Development And Utilization, Salah Ud-Din Khan, Alexander Nakhabov


Варианты приобретения
Цена: 224570.00T
Кол-во:
Наличие: Поставка под заказ.  Есть в наличии на складе поставщика.
Склад Америка: 200 шт.  
При оформлении заказа до: 2025-07-28
Ориентировочная дата поставки: Август-начало Сентября
При условии наличия книги у поставщика.

Добавить в корзину
в Мои желания

Автор: Salah Ud-Din Khan, Alexander Nakhabov
Название:  Nuclear Reactor Technology Development And Utilization
Перевод названия: Салах Уд-Дин Хан, Александр Нахабов: Разработка и использование технологии работы ядерного реактора
ISBN: 9780128184837
Издательство: Elsevier Science
Классификация:




ISBN-10: 0128184833
Обложка/Формат: Paperback
Страницы: 250
Вес: 0.38 кг.
Дата издания: 01.06.2020
Серия: Woodhead publishing series in energy
Язык: English
Размер: 229 x 152 x 26
Ссылка на Издательство: Link
Рейтинг:
Поставляется из: Европейский союз
Описание:

Nuclear Reactor Technology Development and Utilization presents the theory and principles of the most common advanced nuclear reactor systems and provides a context for the value and utilization of nuclear power in a variety of applications both inside and outside a traditional nuclear setting. As countries across the globe realize their plans for a sustainable energy future, the need for innovative nuclear reactor design is increasing, and this book will provide a deep understanding of how these technologies can aid in a regions goal for clean and reliable energy.

Dr Khan and Dr Nakhabov, alongside their team of expert contributors, discuss a variety of important topics, including nuclear fuel cycles, plant decommissioning and hybrid energy systems, while considering a variety of diverse uses such as nuclear desalination, hydrogen generation and radioisotope production. Knowledge acquired enables the reader to conduct further research in academia and industry, and apply the latest design, development, integration, safety and economic guidance to their work and research.



Nuclear reactor analysis

Автор: Duderstadt, James J. Hamilton, Louis J.
Название: Nuclear reactor analysis
ISBN: 0471223638 ISBN-13(EAN): 9780471223634
Издательство: Wiley
Рейтинг:
Цена: 290350.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores.

Fractional-Order Models For Nuclear Reactor Analysis

Автор: Paredes, Gilberto Espinos
Название: Fractional-Order Models For Nuclear Reactor Analysis
ISBN: 0128236655 ISBN-13(EAN): 9780128236659
Издательство: Elsevier Science
Рейтинг:
Цена: 185270.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.

Thermal-Hydraulics of Water Cooled Nuclear Reactors

Автор: D`Auria, Francesco
Название: Thermal-Hydraulics of Water Cooled Nuclear Reactors
ISBN: 0081006624 ISBN-13(EAN): 9780081006627
Издательство: Elsevier Science
Рейтинг:
Цена: 297560.00 T
Наличие на складе: Поставка под заказ.
Описание:

Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors.

Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes.

The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis.

This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability.


Название: Applicability of Design Safety Requirements to Small Modular Reactor Technologies Intended for Near Term Deployment: Light Water Reactors High Temperature Gas Cooled Reactors
ISBN: 9201308205 ISBN-13(EAN): 9789201308207
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 17550.00 T
Наличие на складе: Нет в наличии.
Описание: IAEA Member States have expressed relevant interest in the development and deployment of small and medium-sized or modular reactors (SMRs) to help cover their energy needs in the coming decades. SMR designs may include technological characteristics that differ significantly from those of the large nuclear power plants that are commercially available. Those SMR characteristics can represent a challenge when the existing design requirements, as established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) Safety of Nuclear Power Plants: Design, are intended to be applied to SMRs. This publication focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs. The publication includes the common ground reached by representatives from regulatory bodies, technical and scientific support organizations (TSOs) and SMR design organizations regarding the applicability of the design requirements to both SMR technologies. The insights provided are also intended to contribute to motivating further progress in the harmonization of national and international views on safety approaches for SMR technologies. This publication is intended for use by organizations dealing with nuclear power plant design or operation, and by regulatory bodies and TSOs, particularly from countries that are initiating or enlarging nuclear power programmes that include SMR units.

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment

Автор: Joshi, Jyeshtharaj
Название: Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment
ISBN: 0081023375 ISBN-13(EAN): 9780081023372
Издательство: Elsevier Science
Рейтинг:
Цена: 280720.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors.

Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.

  • Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors
  • Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future
  • Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization

Accident-Tolerant Materials For Light Water Reactor Fuels

Автор: Rebak, Raul B.
Название: Accident-Tolerant Materials For Light Water Reactor Fuels
ISBN: 0128175036 ISBN-13(EAN): 9780128175033
Издательство: Elsevier Science
Рейтинг:
Цена: 176290.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание:

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic.


Название: Advances in High Temperature Gas Cooled Reactor Fuel Technology
ISBN: 9201253109 ISBN-13(EAN): 9789201253101
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: Reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments.

Название: Structural Materials for Liquid Metal Cooled Fast Reactor Fuel Assemblies: Operational Behaviour
ISBN: 9201275102 ISBN-13(EAN): 9789201275103
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 28650.00 T
Наличие на складе: Невозможна поставка.
Описание: Summarizes the findings of several IAEA meetings on fast reactor materials and provides a review of historically available and new information on the properties, fabrication technologies and irradiation behaviour of stainless steel structural materials for liquid metal cooled fast reactor (LMFR) fuel assemblies.

Behaviour of spent power reactor fuel during storage

Название: Behaviour of spent power reactor fuel during storage
ISBN: 9201003196 ISBN-13(EAN): 9789201003195
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: Focuses on the storage of spent nuclear fuel from power reactors - a topic of increasing importance to Member States. To support their needs, the IAEA has carried out successive coordinated research projects on spent fuel performance and the behaviour of spent fuel assemblies in storage since the 1980s. This publication consolidates their findings.

Nuclear Reactor Kinetics and Plant Control

Автор: Yoshiaki Oka; Katsuo Suzuki
Название: Nuclear Reactor Kinetics and Plant Control
ISBN: 4431541942 ISBN-13(EAN): 9784431541943
Издательство: Springer
Рейтинг:
Цена: 158380.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book covers both basic theory of nuclear reactor kinetics/control and state-of-the-art practice in working plants. The first part focuses on fundamental nuclear kinetics, and the second surveys the theories and practice of nuclear power plant control.

Benchmarking of computational fluid dynamics codes for reactor vessel design

Автор: Iaea
Название: Benchmarking of computational fluid dynamics codes for reactor vessel design
ISBN: 9201074204 ISBN-13(EAN): 9789201074201
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: This publication provides a description of the Rossendorf coolant mixing (ROCOM) test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock (PTS) and boron dilution, the calculation results using computational fluid dynamics (CFD) codes and methods, and the conclusions drawn from comparison of CFD results with experimental measurements. The aim of this benchmarking was to provide CFD practitioners with two high quality datasets of relevance to reactor transients inside a pressurized water reactor pressure vessel with different configurations and involving mixed convection, stratification, jet impingement and unsteady (inverse) plumes. The focus of the benchmarking was on the three main regions of the cold domain of the primary circuit, i.e. the cold leg, the downcomer and the core entry region. The work was carried out within the framework of an IAEA coordinated research project on application of computational fluid dynamics codes to nuclear power plant design.

Название: Specific Considerations and Milestones for a Research Reactor Project
ISBN: 9201276109 ISBN-13(EAN): 9789201276100
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 30490.00 T
Наличие на складе: Невозможна поставка.
Описание: Sets out the four phases of a research reactor project with their associated milestones, starting with a careful assessment of the need for the research reactor, the issues it raises and the measures to address them. The publication provides a framework for self-assessment of readiness for a research reactor project.


Казахстан, 010000 г. Астана, проспект Туран 43/5, НП2 (офис 2)
ТОО "Логобук" Тел:+7 707 857-29-98 ,+7(7172) 65-23-70 www.logobook.kz
Kaspi QR
   В Контакте     В Контакте Мед  Мобильная версия