Multilingual Dictionary of Nuclear Reactor Physics and Engineering, Anglart, Henryk
Название: Closed nuclear fuel cycle with fast reactors ISBN: 0323993087 ISBN-13(EAN): 9780323993081 Издательство: Elsevier Science Рейтинг: Цена: 139470.00 T Наличие на складе: Есть 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: Salah Ud-Din Khan, Alexander Nakhabov Название: Nuclear Reactor Technology Development And Utilization ISBN: 0128184833 ISBN-13(EAN): 9780128184837 Издательство: Elsevier Science Рейтинг: Цена: 224570.00 T Наличие на складе: Есть у поставщика Поставка под заказ. 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 region's 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.
Автор: Anglart, Henryk Название: Multilingual Dictionary of Nuclear Reactor Physics and Engineering ISBN: 0367470810 ISBN-13(EAN): 9780367470814 Издательство: Taylor&Francis Рейтинг: Цена: 148010.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This multilingual dictionary explains, in simple and clear language, the most frequently-used terms and expressions in the field of nuclear reactor physics and engineering, and provides translations of these terms from English into French, German, Swedish and Polish.
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.
Автор: Tucker, Colin Название: How to drive a nuclear reactor ISBN: 3030338754 ISBN-13(EAN): 9783030338756 Издательство: Springer Рейтинг: Цена: 26080.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: Along the way it covers a bit of the engineering, reactor history, different kinds of reactors and what can go wrong with them. Much of this is seen from the viewpoint of a trainee operator on a Pressurised Water Reactor - the most common type of nuclear reactor in the world.
Автор: Anatoly Lanin Название: Nuclear Rocket Engine Reactor ISBN: 3642442633 ISBN-13(EAN): 9783642442636 Издательство: Springer Рейтинг: Цена: 95770.00 T Наличие на складе: Есть у поставщика Поставка под заказ. Описание: This book details the development of a nuclear rocket engine reactor, based on simulation experiments and prototype reactor test data. Covers properties and performance of materials and fuels, and reviews prospects for use in piloted and drone spacecraft.
Автор: Hensley Trenton Название: Nuclear Reactor Physics ISBN: 1632387077 ISBN-13(EAN): 9781632387073 Издательство: Неизвестно Рейтинг: Цена: 171660.00 T Наличие на складе: Есть у поставщика Поставка под заказ.
Название: Approaches to Safety Evaluation of New and Existing Research Reactor Facilities in Relation to External Events ISBN: 920102617X ISBN-13(EAN): 9789201026170 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 38450.00 T Наличие на складе: Нет в наличии. Описание: This publication provides information and a framework for Member States to conduct realistic safety evaluation for research reactors in terms of external events. The publication provides information with examples on the use of a graded approach, based on the radiological hazard that a facility poses to the environment, public and workers, and takes into account the lessons from the Fukushima accident. This publication supports the development of site specific guidelines for the actual design and safety assessment, and should be used in conjunction with the relevant IAEA Safety Standards. It can also be used as training material for research reactor staff and for a self-assessment of the vulnerability of existing structures to external events.
Автор: Demaziere, Christophe Название: Modelling Of Nuclear Reactor Multi-Physics ISBN: 0128150696 ISBN-13(EAN): 9780128150696 Издательство: Elsevier Science Рейтинг: Цена: 158330.00 T 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.
Название: Reliability Data for Research Reactor Probabilistic Safety Assessment ISBN: 9201143206 ISBN-13(EAN): 9789201143204 Издательство: Mare Nostrum (Eurospan) Рейтинг: Цена: 16630.00 T Наличие на складе: Невозможна поставка. Описание: Provides information on reliability data for research reactors. In addition to component reliability data, the publication provides useful information related to the preparation and application of data relevant to initiating events, human reliability, and common cause failures.
