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High Temperature Gas Reactors

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Modular High temperature Gas cooled Reactor Power Plant

Modular High temperature Gas cooled Reactor Power Plant Book
Author : Kurt Kugeler,Zuoyi Zhang
Publisher : Springer
Release : 2018-08-25
ISBN : 9783662577103
Language : En, Es, Fr & De

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Book Description :

"Modular High-temperature Gas-cooled Reactor Power Plant" introduces the power plants driven by modular high temperature gas-cooled reactors (HTR), which are characterized by their inherent safety features and high output temperatures. HTRs have the potential to be adopted near demand side to supply both electricity and process heat, directly replacing conventional fossil fuels. The world is confronted with two dilemmas in the energy sector, namely climate change and energy supply security. HTRs have the potential to significantly alleviate these concerns. This book will provide readers with a thorough understanding of HTRs, their history, principles, and fields of application. The book is intended for researchers and engineers involved with nuclear engineering and energy technology.

High Temperature Gas cooled Reactors

High Temperature Gas cooled Reactors Book
Author : Tetsuaki Takeda,Yoshiyuki Inagaki
Publisher : Academic Press
Release : 2021-02-24
ISBN : 012821032X
Language : En, Es, Fr & De

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Book Description :

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.

Integration of High Temperature Gas Reactors with in Situ Oil Shale Retorting

Integration of High Temperature Gas Reactors with in Situ Oil Shale Retorting Book
Author : Anonim
Publisher : Unknown
Release : 2011
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

This paper evaluates the integration of a high-temperature gas-cooled reactor (HTGR) to an in situ oil shale retort operation producing 7950 m3/D (50,000 bbl/day). The large amount of heat required to pyrolyze the oil shale and produce oil would typically be provided by combustion of fossil fuels, but can also be delivered by an HTGR. Two cases were considered: a base case which includes no nuclear integration, and an HTGR-integrated case.

Semi homogeneous High temperature Gas cooled Breeder Reactors

Semi homogeneous High temperature Gas cooled Breeder Reactors Book
Author : K. Inoue,T. Kuroyanagi,S. Yajima
Publisher : Unknown
Release : 1962
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Download Semi homogeneous High temperature Gas cooled Breeder Reactors book written by K. Inoue,T. Kuroyanagi,S. Yajima, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

The Integration of Process Heat Applications to High Temperature Gas Reactors

The Integration of Process Heat Applications to High Temperature Gas Reactors Book
Author : Anonim
Publisher : Unknown
Release : 2011
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

A high temperature gas reactor, HTGR, can produce industrial process steam, high-temperature heat-transfer gases, and/or electricity. In conventional industrial processes, these products are generated by the combustion of fossil fuels such as coal and natural gas, resulting in significant emissions of greenhouse gases such as carbon dioxide. Heat or electricity produced in an HTGR could be used to supply process heat or electricity to conventional processes without generating any greenhouse gases. Process heat from a reactor needs to be transported by a gas to the industrial process. Two such gases were considered in this study: helium and steam. For this analysis, it was assumed that steam was delivered at 17 MPa and 540 C and helium was delivered at 7 MPa and at a variety of temperatures. The temperature of the gas returning from the industrial process and going to the HTGR must be within certain temperature ranges to maintain the correct reactor inlet temperature for a particular reactor outlet temperature. The returning gas may be below the reactor inlet temperature, ROT, but not above. The optimal return temperature produces the maximum process heat gas flow rate. For steam, the delivered pressure sets an optimal reactor outlet temperature based on the condensation temperature of the steam. ROTs greater than 769.7 C produce no additional advantage for the production of steam.

An Evaluation of High temperature Gas cooled Reactors

An Evaluation of High temperature Gas cooled Reactors Book
Author : Oak Ridge National Laboratory
Publisher : Unknown
Release : 1969
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Download An Evaluation of High temperature Gas cooled Reactors book written by Oak Ridge National Laboratory, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

Preliminary Results of the Combined Third and Fourth Very High Temperature Gas Cooled Reactor Irradiation in the Advanced Test Reactor

Preliminary Results of the Combined Third and Fourth Very High Temperature Gas Cooled Reactor Irradiation in the Advanced Test Reactor Book
Author : Anonim
Publisher : Unknown
Release : 2001
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

The United States Department of Energy's Very High Temperature Reactor Technology Development Office (VHTR-TDO) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is irradiating up to seven low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation high temperature gas-cooled reactors in the United States. The experiments will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of several independent capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and was completed in November 2009. The second experiment (AGR-2) started irradiation in June 2010 and completed in October 2013. The third and fourth experiments were combined into a single experiment designated (AGR-3/4), which started its irradiation in December 2011 and completed in April 2014. Since the purpose of this combined experiment was to provide data on fission product migration and retention in a high temperature gas-cooled reactor (HTGR), the design of this experiment was significantly different from the first two experiments, though the control and monitoring systems are extremely similar. The design of the experiment will be discussed followed by its progress and status to date.

Development of Compact Heat Exchangers for Very High temperature Gas cooled Reactors

Development of Compact Heat Exchangers for Very High temperature Gas cooled Reactors Book
Author : Sai K. Mylavarapu
Publisher : Unknown
Release : 2008
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Abstract: The U.S. Department of Energy's Generation IV Program has generated considerable interest for High-Temperature Gas-Cooled Reactors (HTGR), in particular, the Very-High-Temperature Reactor (VHTR). VHTR is one of the six reactor concepts selected by the Generation IV International Forum and is anticipated to be reactor type for the Next Generation Nuclear Plant (NGNP). The VHTR concept, with a projected plant design service life of 60 years, is being actively researched not only due to its near-term deployment potential but also because it offers a broad range of process heat applications ranging from electricity generation to hydrogen co-generation. To efficiently and reliably transfer the thermal output from the reactor core, VHTRs require high temperature (900-950 0C) and high integrity heat exchangers with high effectiveness during normal and off-normal conditions. A class of compact plate-type heat exchangers, namely, Printed Circuit Heat Exchangers (PCHEs), made of high-temperature materials and found to have these above characteristics are being increasingly pursued for heavy duty applications. The current thesis work is a part of a larger research project aimed at investigating the design, fabrication, testing, modeling, and optimization of PCHEs at operating temperatures proposed to be realized in VHTRs. In the present work, two PCHEs were designed and fabricated. In addition, a detailed design of a high-temperature helium test facility to test the thermal-hydraulic performance of these PCHEs was completed. Owing to the high operating temperatures and pressures, a detailed investigation on various high-temperature materials was carried out to aid in the design of the test facility and the heat exchangers. The study showed that Alloys 617 and 230 are the leading candidate materials for high-temperature applications. However, economics and material availability in the required form dictated the final design operating conditions. The helium test facility is of Alloy 800HT construction and is currently being constructed at The Ohio State University. It is intended to facilitate experiments at operating temperatures and pressures up to 900 0C and 3 MPa, respectively. Two PCHEs, each having 10 hot and 10 cold plates with 12 channels in each plate, were fabricated using Alloy 617 plates. In addition, the processes related to the fabrication of PCHEs, namely photochemical machining and diffusion bonding techniques were investigated and successfully established for Alloy 617 plates. The PCHEs will be tested in the helium test facility for their heat transfer and pressure drop characteristics at various operating temperatures and pressures. The experimental database generated from the test facility will then be used for model development and computer code validation. In summary, the current thesis focuses on the study of the high-temperature materials, design of the helium test facility, design, development, and fabrication of the high-temperature PCHEs.

Advanced and High temperature Gas cooled Reactors

Advanced and High temperature Gas cooled Reactors Book
Author : Anonim
Publisher : Unknown
Release : 1969
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Fuel Cycle and Nuclear Material Disposition Issues Associated with High Temperature Gas Reactors

Fuel Cycle and Nuclear Material Disposition Issues Associated with High Temperature Gas Reactors Book
Author : D. E. Shropshire,J. S. Herring
Publisher : Unknown
Release : 2004
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim storage, packaging, transportation, waste forms, waste treatment, decontamination and decommissioning issues; and low-level waste (LLW) and high-level waste (HLW) disposal.

Modular High temperature Gas cooled Reactor Power Plant

Modular High temperature Gas cooled Reactor Power Plant Book
Author : Kurt Kugeler,Zuoyi Zhang
Publisher : Springer
Release : 2018-12-16
ISBN : 9783662586068
Language : En, Es, Fr & De

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Book Description :

"Modular High-temperature Gas-cooled Reactor Power Plant" introduces the power plants driven by modular high temperature gas-cooled reactors (HTR), which are characterized by their inherent safety features and high output temperatures. HTRs have the potential to be adopted near demand side to supply both electricity and process heat, directly replacing conventional fossil fuels. The world is confronted with two dilemmas in the energy sector, namely climate change and energy supply security. HTRs have the potential to significantly alleviate these concerns. This book will provide readers with a thorough understanding of HTRs, their history, principles, and fields of application. The book is intended for researchers and engineers involved with nuclear engineering and energy technology.

High Temperature Gas Cooled Reactor Technology Development Program

High Temperature Gas Cooled Reactor Technology Development Program Book
Author : Anonim
Publisher : Unknown
Release : 1989
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

The High-Temperature Gas-Cooled Reactor (HTGR) Program being carried out under the US Department of Energy (DOE) continues to emphasize the development of modular high-temperature gas-cooled reactors (MHTGRs) possessing a high degree of inherent safety. The emphasis at this time is to develop the preliminary design of the reference MHTGR and to develop the associated technology base and licensing infrastructure in support of future reactor deployment. A longer-term objective is to realize the full high-temperature potential of HTGRs in gas turbine and high-temperature, process-heat applications. This document summarizes the activities of the HTGR Technology Development Program for the period ending December 31, 1987.

Evaluation of Modular High Temperature Gas cooled Reactors

Evaluation of Modular High Temperature Gas cooled Reactors Book
Author : P. Levin
Publisher : Unknown
Release : 1994
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Download Evaluation of Modular High Temperature Gas cooled Reactors book written by P. Levin, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

Design Configurations and Coupling High Temperature Gas Cooled Reactor and Hydrogen Plant

Design Configurations and Coupling High Temperature Gas Cooled Reactor and Hydrogen Plant Book
Author : Anonim
Publisher : Unknown
Release : 2008
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant (NGNP), may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single- and dual-purpose facilities need to be understood.

Rapid Depressurization of a Thermal Insulation System for High Temperature Gas Reactors

Rapid Depressurization of a Thermal Insulation System for High Temperature Gas Reactors Book
Author : E. Aranovitch,D. van Asselt
Publisher : Unknown
Release : 1972
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Download Rapid Depressurization of a Thermal Insulation System for High Temperature Gas Reactors book written by E. Aranovitch,D. van Asselt, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

Computational Flow Predictions for the Lower Plenum of a High Temperature Gas Cooled Reactor

Computational Flow Predictions for the Lower Plenum of a High Temperature  Gas Cooled Reactor Book
Author : Anonim
Publisher : Unknown
Release : 2006
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety over present day nuclear reactors. Accurate simulation models of these Generation IV reactors are necessary for design and licensing. One design under consideration by the Very High Temperature Reactor (VHTR) program is a modular, prismatic gas-cooled reactor. In this reactor, the lower plenum region may experience locally high temperatures that can adversely impact the plant's structural integrity. Since existing system analysis codes cannot capture the complex flow effects occurring in the lower plenum, computational fluid dynamics (CFD) codes are being employed to model these flows [1]. The goal of the present study is to validate the CFD calculations using experimental data.

High temperature gas cooled reactors

High temperature gas cooled reactors Book
Author : Nihon Genshiryoku Kenkyūjo
Publisher : Unknown
Release : 1992
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

Download High temperature gas cooled reactors book written by Nihon Genshiryoku Kenkyūjo, available in PDF, EPUB, and Kindle, or read full book online anywhere and anytime. Compatible with any devices.

Integration of High Temperature Gas Cooled Reactors Into Industrial Process Applications

Integration of High Temperature Gas Cooled Reactors Into Industrial Process Applications Book
Author : Anonim
Publisher : Unknown
Release : 2011
ISBN : 0987650XXX
Language : En, Es, Fr & De

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Book Description :

This report is a summary of analyses performed by the NGNP project to determine whether it is technically and economically feasible to integrate high temperature gas cooled reactor (HTGR) technology into industrial processes. To avoid an overly optimistic environmental and economic baseline for comparing nuclear integrated and conventional processes, a conservative approach was used for the assumptions and calculations.