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Structural Materials for Heavy Liquid Metal Cooled Fast Reactors: Proceedings of a Technical Meeting, 


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Название:  Structural Materials for Heavy Liquid Metal Cooled Fast Reactors: Proceedings of a Technical Meeting
ISBN: 9789201288219
Издательство: Mare Nostrum (Eurospan)
Классификация:

ISBN-10: 9201288212
Обложка/Формат: Paperback
Страницы: 240
Вес: 0.65 кг.
Дата издания: 30.11.2021
Серия: Economics/Business/Finance
Язык: English
Иллюстрации: 162 illustrations
Размер: 297 x 210
Читательская аудитория: Professional and scholarly
Ключевые слова: Nuclear power & engineering,Nuclear power industries
Подзаголовок: Proceedings of a technical meeting
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Поставляется из: Англии
Описание: To understand the current status of the research and development as well as to provide a forum to exchange information on structural materials for HLM cooled reactors, the IAEA organised a technical meeting. This resulted in the current publication.

Closed nuclear fuel cycle with fast reactors

Название: Closed nuclear fuel cycle with fast reactors
ISBN: 0323993087 ISBN-13(EAN): 9780323993081
Издательство: Elsevier Science
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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.


Dynamic simulation of sodium cooled fast reactors /

Автор: Vaidyanathan, G.,
Название: Dynamic simulation of sodium cooled fast reactors /
ISBN: 1032254351 ISBN-13(EAN): 9781032254357
Издательство: Taylor&Francis
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Цена: 122490.00 T
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Описание: The text comprehensively discusses basis of mathematical modelling of the heat transfer process in a fast reactor cooled by sodium in a single volume. The text will be helpful for senior undergraduate, graduate students and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.

Safety of Sodium-Cooled Fast Reactors: Particle-Bed-Related Phenomena in Severe Accidents

Автор: Cheng Songbai, Xu Ruicong
Название: Safety of Sodium-Cooled Fast Reactors: Particle-Bed-Related Phenomena in Severe Accidents
ISBN: 9811661154 ISBN-13(EAN): 9789811661150
Издательство: Springer
Цена: 102480.00 T
Наличие на складе: Есть у поставщика Поставка под заказ.
Описание: This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems.

Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident

Название: Developments in the Analysis and Management of Combustible Gases in Severe Accidents in Water Cooled Reactors following the Fukushima Daiichi Accident
ISBN: 9201320205 ISBN-13(EAN): 9789201320209
Издательство: Mare Nostrum (Eurospan)
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Цена: 16630.00 T
Наличие на складе: Нет в наличии.
Описание: Reviews the current state of technology regarding combustible gas related safety issues in water cooled nuclear reactors, with a specific focus on post-Fukushima Daiichi accident developments. The recent results obtained from experimental and analytical research on hydrogen/combustible gas behaviour are discussed.

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)
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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.

Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors

Название: Natural Circulation Phenomena and Modelling for Advanced Water Cooled Reactors
ISBN: 9201274106 ISBN-13(EAN): 9789201274106
Издательство: Mare Nostrum (Eurospan)
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Цена: 16630.00 T
Наличие на складе: Невозможна поставка.
Описание: Covers the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems; characterization of each phenomenon; integral tests to examine the passive systems and natural circulation; and a methodology for examining passive system reliability.

Sodium-Cooled Fast Reactors,3

Автор: Morishita, Masaki
Название: Sodium-Cooled Fast Reactors,3
ISBN: 0128240768 ISBN-13(EAN): 9780128240762
Издательство: Elsevier Science
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Цена: 174050.00 T
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.

High Temperature Gas-Cooled Reactors

Автор: Takeda Tetsuaki, Inagaki Yoshiyuki
Название: High Temperature Gas-Cooled Reactors
ISBN: 0128210311 ISBN-13(EAN): 9780128210314
Издательство: Elsevier Science
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Цена: 174050.00 T
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.


Supercritical-Pressure Light Water Cooled Reactors

Автор: Yoshiaki Oka; Hideo Mori
Название: Supercritical-Pressure Light Water Cooled Reactors
ISBN: 4431550240 ISBN-13(EAN): 9784431550242
Издательство: Springer
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Цена: 113190.00 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
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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: Review of Fuel Failures in Water Cooled Reactors (2006–2015) (Russian Edition)
ISBN: 9204295201 ISBN-13(EAN): 9789204295207
Издательство: Mare Nostrum (Eurospan)
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Цена: 32340.00 T
Наличие на складе: Нет в наличии.
Описание: Since the 1970s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (nonaccident) operational conditions. This updated version of IAEA Nuclear Energy Series No. NFT2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

Materials and Water Chemistry for Supercritical Water-cooled Reactors

Автор: Guzonas, David
Название: Materials and Water Chemistry for Supercritical Water-cooled Reactors
ISBN: 008102049X ISBN-13(EAN): 9780081020494
Издательство: Elsevier Science
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Цена: 179660.00 T
Наличие на складе: Поставка под заказ.
Описание:

Materials and Water Chemistry for Supercritical Water-cooled Reactors uniquely brings together materials and water chemistry, highlighting their interrelationship, their historical perspective, and their application to SCWR conceptual design. Written by world leading experts, all active in the area of materials and chemistry R&D in support of GEN IV SCWR, this book presents a comprehensive reference on the topics, and in particular, how their data relate to the SCWR design itself. It is an essential text for researchers in the areas of supercritical water cooled reactor materials and chemistry.

In addition, the book gives newcomers to the field a survey of all of the available literature and a clear understanding of how these studies relate to the design of the SCWR concept. The material presented is at a specialist's level in materials or corrosion science, or in water chemistry of power plants.


  • Provides comprehensive coverage of the chemistry and materials of SCWR
  • Presents the latest research and results condensed into one book
  • Covers the differences in use of SCW in nuclear reactors and fossil plants, and the resulting differences in materials requirements


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