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Simulated Nuclear Reactor System For High Temperature Process Heat

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Simulated Nuclear Reactor System For High Temperature Process Heat

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Author : Neil H. Coates
language : en
Publisher:
Release Date : 1961

Simulated Nuclear Reactor System For High Temperature Process Heat written by Neil H. Coates and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Nuclear engineering categories.

Simulated Nuclear Reactor System For High Temperature Process Heat

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Author : Aaron G. Starliper
language : en
Publisher:
Release Date : 1961

Simulated Nuclear Reactor System For High Temperature Process Heat written by Aaron G. Starliper and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Aluminum silicates categories.

Development Of A Simulated High Temperature Nuclear Loop

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Author : James P. McGee
language : en
Publisher:
Release Date : 1960

Development Of A Simulated High Temperature Nuclear Loop written by James P. McGee and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Heat categories.

High Temperature Systems For Nuclear Process Heat

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Author : James P. McGee
language : en
Publisher:
Release Date : 1960

High Temperature Systems For Nuclear Process Heat written by James P. McGee and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1960 with Heat categories.

High Temperature Gas Cooled Reactors

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Author : Tetsuaki Takeda
language : en
Publisher: Academic Press
Release Date : 2021-02-24

High Temperature Gas Cooled Reactors written by Tetsuaki Takeda and has been published by Academic Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2021-02-24 with Business & Economics categories.

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. Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits Considers the societal impact and sustainability concerns and goals throughout the discussion Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems.

An Indirect Cycle Nuclear Reactor System To Furnish Process Heat Engineering And Design Concepts

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Author : R. Carson Dalzell
language : en
Publisher:
Release Date : 1959

An Indirect Cycle Nuclear Reactor System To Furnish Process Heat Engineering And Design Concepts written by R. Carson Dalzell and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Coal gasification categories.

Bureau Of Mines Research And Technologic Work On Coal 1959

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Author : United States. Bureau of Mines
language : en
Publisher:
Release Date : 1962

Bureau Of Mines Research And Technologic Work On Coal 1959 written by United States. Bureau of Mines and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1962 with Coal categories.