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Handbook On Thermal Hydraulics In Water-Cooled Nuclear Reactors, D`Auria,Francesco


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Автор: D`Auria,Francesco
Название:  Handbook On Thermal Hydraulics In Water-Cooled Nuclear Reactors
ISBN: 9780323856089
Издательство: Elsevier Science
Классификация:

ISBN-10: 032385608X
Обложка/Формат: Paperback
Страницы: 600
Вес: 0.00 кг.
Дата издания: 01.06.2024
Серия: Woodhead publishing series in energy
Размер: 229 x 151
Основная тема: Engineering
Подзаголовок: Volume 3: procedures and applications
Ссылка на Издательство: Link
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Поставляется из: Европейский союз


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: 20920.00 р. 23244.00 -10%
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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: 18374.00 р.
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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.

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: 26107.00 р.
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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.

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: 26107.00 р.
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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.

Technical Insights from Benchmarking Different Methods for Predicting Pipe Failure Rates in Water Cooled Reactors

Название: Technical Insights from Benchmarking Different Methods for Predicting Pipe Failure Rates in Water Cooled Reactors
ISBN: 9201411219 ISBN-13(EAN): 9789201411211
Издательство: Mare Nostrum (Eurospan)
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Цена: 2495.00 р.
Наличие на складе: Нет в наличии.

Описание: Presents the outcome of an IAEA coordinated research project (CRP) on methodologies for assessing pipe failure rates in advanced water cooled reactors. The goal of the CRP was to provide Member States with a strong technical basis for establishing nuclear power plant piping reliability parameters.

Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors

Название: Status and Evaluation of Severe Accident Simulation Codes for Water Cooled Reactors
ISBN: 9201029195 ISBN-13(EAN): 9789201029195
Издательство: Mare Nostrum (Eurospan)
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Цена: 2495.00 р.
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Описание: Summarizes the current status of severe accident analysis codes and recommends areas for research and development. The information is detailed in terms of major findings,

Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs): Final Report of a Coordinated Research Project

Название: Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs): Final Report of a Coordinated Research Project
ISBN: 9201023200 ISBN-13(EAN): 9789201023209
Издательство: Mare Nostrum (Eurospan)
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Цена: 2495.00 р.
Наличие на складе: Нет в наличии.

Описание: Illustrates the state of the art in supercritical water cooled reactor (SCWR) research and development. This is a key supporting publication to researchers and engineers pursuing the development of SCWRs or equipment/components operating at supercritical pressures.

Название: Review of Fuel Failures in Water Cooled Reactors (2006–2015): An Update of IAEA Nuclear Energy Series No. NF-T-2.1
ISBN: 9201043198 ISBN-13(EAN): 9789201043191
Издательство: Mare Nostrum (Eurospan)
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Цена: 4851.00 р.
Наличие на складе: Нет в наличии.

Описание: Since the 1970`s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (non-accident) operational conditions. This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.

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: 16979.00 р.
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Название: Review of Fuel Failures in Water Cooled Reactors (2006–2015) (Russian Edition)
ISBN: 9204295201 ISBN-13(EAN): 9789204295207
Издательство: Mare Nostrum (Eurospan)
Рейтинг:
Цена: 4851.00 р.
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.

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: 2495.00 р.
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: 2633.00 р.
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.


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