High Temperature Gas cooled Reactors

High Temperature Gas cooled Reactors
Author: Tetsuaki Takeda,Yoshiyuki Inagaki
Publsiher: Academic Press
Total Pages: 478
Release: 2021-02-24
ISBN 10: 012821032X
ISBN 13: 9780128210321
Language: EN, FR, DE, ES & NL

High Temperature Gas cooled Reactors Book Review:

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.

Modular High temperature Gas cooled Reactor Power Plant

Modular High temperature Gas cooled Reactor Power Plant
Author: Kurt Kugeler,Zuoyi Zhang
Publsiher: Springer
Total Pages: 893
Release: 2018-08-25
ISBN 10: 9783662577103
ISBN 13: 3662577100
Language: EN, FR, DE, ES & NL

Modular High temperature Gas cooled Reactor Power Plant Book Review:

"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.

Modular High temperature Gas cooled Reactor Power Plant

Modular High temperature Gas cooled Reactor Power Plant
Author: Kurt Kugeler,Zuoyi Zhang
Publsiher: Springer
Total Pages: 893
Release: 2018-10-05
ISBN 10: 3662577127
ISBN 13: 9783662577127
Language: EN, FR, DE, ES & NL

Modular High temperature Gas cooled Reactor Power Plant Book Review:

"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.

Physics of High Temperature Reactors

Physics of High Temperature Reactors
Author: Luigi Massimo
Publsiher: Elsevier
Total Pages: 224
Release: 2013-10-22
ISBN 10: 1483280284
ISBN 13: 9781483280288
Language: EN, FR, DE, ES & NL

Physics of High Temperature Reactors Book Review:

Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.

The Integration of Process Heat Applications to High Temperature Gas Reactors

The Integration of Process Heat Applications to High Temperature Gas Reactors
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: OCLC:873873633
Language: EN, FR, DE, ES & NL

The Integration of Process Heat Applications to High Temperature Gas Reactors Book Review:

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
Author: Oak Ridge National Laboratory
Publsiher: Unknown
Total Pages: 220
Release: 1969
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015095068352
Language: EN, FR, DE, ES & NL

An Evaluation of High temperature Gas cooled Reactors Book Review:

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
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2001
ISBN 10: 1928374650XXX
ISBN 13: OCLC:925449902
Language: EN, FR, DE, ES & NL

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

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.

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

Integration of High Temperature Gas Reactors with in Situ Oil Shale Retorting
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: OCLC:873646415
Language: EN, FR, DE, ES & NL

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

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.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

Advances in High Temperature Gas Cooled Reactor Fuel Technology
Author: International Atomic Energy Agency
Publsiher: Unknown
Total Pages: 639
Release: 2012-06
ISBN 10: 9789201253101
ISBN 13: 9201253109
Language: EN, FR, DE, ES & NL

Advances in High Temperature Gas Cooled Reactor Fuel Technology Book Review:

This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Advanced and High temperature Gas cooled Reactors

Advanced and High temperature Gas cooled Reactors
Author: Anonim
Publsiher: Unknown
Total Pages: 917
Release: 1969
ISBN 10: 1928374650XXX
ISBN 13: UOM:39015003993642
Language: EN, FR, DE, ES & NL

Advanced and High temperature Gas cooled Reactors Book Review:

High Temperature Gas Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant

High Temperature Gas Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2010
ISBN 10: 1928374650XXX
ISBN 13: OCLC:727268666
Language: EN, FR, DE, ES & NL

High Temperature Gas Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant Book Review:

High Temperature Gas Reactors (HTGR) have been designed and operated throughout the world over the past five decades. These seven HTGRs are varied in size, outlet temperature, primary fluid, and purpose. However, there is much the Next Generation Nuclear Plant (NGNP) has learned and can learn from these experiences. This report captures these various experiences and documents the lessons learned according to the physical NGNP hardware (i.e., systems, subsystems, and components) affected thereby.

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

Development of Compact Heat Exchangers for Very High temperature Gas cooled Reactors
Author: Sai K. Mylavarapu
Publsiher: Unknown
Total Pages: 110
Release: 2008
ISBN 10: 1928374650XXX
ISBN 13: OCLC:289031385
Language: EN, FR, DE, ES & NL

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

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.

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

Design Configurations and Coupling High Temperature Gas Cooled Reactor and Hydrogen Plant
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2008
ISBN 10: 1928374650XXX
ISBN 13: OCLC:727355209
Language: EN, FR, DE, ES & NL

Design Configurations and Coupling High Temperature Gas Cooled Reactor and Hydrogen Plant Book Review:

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.

Material Control and Accounting Design Considerations for High Temperature Gas Reactors

Material Control and Accounting Design Considerations for High Temperature Gas Reactors
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: OCLC:873875212
Language: EN, FR, DE, ES & NL

Material Control and Accounting Design Considerations for High Temperature Gas Reactors Book Review:

The subject of this report is domestic safeguards and security by design (2SBD) for high-temperature gas reactors, focusing on material control and accountability (MC & A). The motivation for the report is to provide 2SBD support to the Next Generation Nuclear Plant (NGNP) project, which was launched by Congress in 2005. This introductory section will provide some background on the NGNP project and an overview of the 2SBD concept. The remaining chapters focus specifically on design aspects of the candidate high-temperature gas reactors (HTGRs) relevant to MC & A, Nuclear Regulatory Commission (NRC) requirements, and proposed MC & A approaches for the two major HTGR reactor types: pebble bed and prismatic. Of the prismatic type, two candidates are under consideration: (1) GA's GT-MHR (Gas Turbine-Modular Helium Reactor), and (2) the Modular High-Temperature Reactor (M-HTR), a derivative of Areva's Antares reactor. The future of the pebble-bed modular reactor (PBMR) for NGNP is uncertain, as the PBMR consortium partners (Westinghouse, PBMR [Pty] and The Shaw Group) were unable to agree on the path forward for NGNP during 2010. However, during the technology assessment of the conceptual design phase (Phase 1) of the NGNP project, AREVA provided design information and technology assessment of their pebble bed fueled plant design called the HTR-Module concept. AREVA does not intend to pursue this design for NGNP, preferring instead a modular reactor based on the prismatic Antares concept. Since MC & A relevant design information is available for both pebble concepts, the pebble-bed HTGRs considered in this report are: (1) Westinghouse PBMR; and (2) AREVA HTR-Module. The DOE Office of Nuclear Energy (DOE-NE) sponsors the Fuel Cycle Research and Development program (FCR & D), which contains an element specifically focused on the domestic (or state) aspects of SBD. This Material Protection, Control and Accountancy Technology (MPACT) program supports the present work summarized in this report, namely the development of guidance to support the consideration of MC & A in the design of both pebble-bed and prismatic-fueled HTGRs. The objective is to identify and incorporate design features into the facility design that will cost effectively aid in making MC & A more effective and efficient, with minimum impact on operations. The theft of nuclear material is addressed through both MC & A and physical protection, while the threat of sabotage is addressed principally through physical protection.

Optimum Reactor Outlet Temperatures for High Temperature Gas Cooled Reactors Integrated with Industrial Processes

Optimum Reactor Outlet Temperatures for High Temperature Gas Cooled Reactors Integrated with Industrial Processes
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: OCLC:873646367
Language: EN, FR, DE, ES & NL

Optimum Reactor Outlet Temperatures for High Temperature Gas Cooled Reactors Integrated with Industrial Processes Book Review:

This report summarizes the results of a temperature sensitivity study conducted to identify the optimum reactor operating temperatures for producing the heat and hydrogen required for industrial processes associated with the proposed new high temperature gas-cooled reactor. This study assumed that primary steam outputs of the reactor were delivered at 17 MPa and 540°C and the helium coolant was delivered at 7 MPa at 625-925°C. The secondary outputs of were electricity and hydrogen. For the power generation analysis, it was assumed that the power cycle efficiency was 66% of the maximum theoretical efficiency of the Carnot thermodynamic cycle. Hydrogen was generated via the hightemperature steam electrolysis or the steam methane reforming process. The study indicates that optimum or a range of reactor outlet temperatures could be identified to further refine the process evaluations that were developed for high temperature gas-cooled reactor-integrated production of synthetic transportation fuels, ammonia, and ammonia derivatives, oil from unconventional sources, and substitute natural gas from coal.

High Temperature Gas Cooled Reactor Fuels and Materials

High Temperature Gas Cooled Reactor Fuels and Materials
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2010
ISBN 10: 1928374650XXX
ISBN 13: OCLC:1132102736
Language: EN, FR, DE, ES & NL

High Temperature Gas Cooled Reactor Fuels and Materials Book Review:

"Member States of the IAEA have pursued activities focused on developing high temperature gas cooled reactors (HTGRs) with an aim to build innovative nuclear fuel cycles and reactor systems for high temperature applications such as process heat and hydrogen production, apart from electricity generation. This publication documents the knowledge and experience in the development of HTGRs gained over fifty years and will serve as a basis for further development of fuels and reactor systems ... Subject Classification : 0802 - Fuel fabrication and performance. Responsible Officer : Mr. Uddharan Basak, NEFW."--Résumé de l'éditeur

Balance of Plant Analysis for High Temperature Gas Cooled Reactors

Balance of Plant Analysis for High Temperature Gas Cooled Reactors
Author: Chunyun Wang
Publsiher: LAP Lambert Academic Publishing
Total Pages: 220
Release: 2009-09
ISBN 10: 9783838313894
ISBN 13: 3838313895
Language: EN, FR, DE, ES & NL

Balance of Plant Analysis for High Temperature Gas Cooled Reactors Book Review:

As a Generation IV nuclear system, the High Temperature Gas Cooled Reactor (HTGR) desires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness. The availability of compact heat exchangers and helium turbo-machinery are thus the critical enabling technology for the gas turbine cycle. This book performs an extensive study on the power conversion system: design constraints, cycle variations, compact heat exchangers, high efficiency helium turbo-machinery and cycle control methods. A detailed steady state and dynamic model is developed for studying the cycle design in terms of efficiency and controllability. An indirect closed helium cycle design is developed in this book by identifying key advances in the technology that could reasonably be expected to be achieved with limited R&D. The modular conceptual design for the intermediate heat exchanger (IHX) and recuperator is also performed.

Facility Configuration Study of the High Temperature Gas Cooled Reactor Component Test Facility

Facility Configuration Study of the High Temperature Gas Cooled Reactor Component Test Facility
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2008
ISBN 10: 1928374650XXX
ISBN 13: OCLC:727355460
Language: EN, FR, DE, ES & NL

Facility Configuration Study of the High Temperature Gas Cooled Reactor Component Test Facility Book Review:

A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: Identifies pre-conceptual design requirements Develops test loop equipment schematics and layout Identifies space allocations for each of the facility functions, as required Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems Identifies pre-conceptual utility and support system needs Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

Air Ingress Analyses on a High Temperature Gas Cooled Reactor

Air Ingress Analyses on a High Temperature Gas Cooled Reactor
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2001
ISBN 10: 1928374650XXX
ISBN 13: OCLC:871368084
Language: EN, FR, DE, ES & NL

Air Ingress Analyses on a High Temperature Gas Cooled Reactor Book Review:

A primary-pipe break accident is one of the design-basis accidents of a high-temperature gas-cooled reactor (HTGR). When this accident occurs, air is anticipated to enter the reactor core from the break and oxidize the in-core graphite structure in the modular pebble bed reactor (MPBR). This paper presents the results of the graphite oxidation model developed as part of the Idaho National Engineering and Environmental Laboratory's Direct Research and Development effort. Although gas reactors have been tried in the past with limited success, the innovations of modularity and integrated state-ofart control systems coupled with improved fuel design and a pebble bed core make this design potentially very attractive from an economic and technical perspective. A schematic diagram on a reference design of the MPBR has been established on a major component level (INEEL & MIT, 1999). Steady-state and transient thermal hydraulics models will be produced with key parameters established for these conditions at all major components. Development of an integrated plant model to allow for transient analysis on a more sophisticated level is now being developed. In this paper, preliminary results of the hypothetical air ingress are presented. A graphite oxidation model was developed to determine temperature and the control mechanism in the spherical graphite geometry.

Reactor Core Design for High temperature Gas cooled Reactors

Reactor Core Design for High temperature Gas cooled Reactors
Author: Kerntechnischer Ausschuss, Köln
Publsiher: Unknown
Total Pages: 4
Release: 1986
ISBN 10: 1928374650XXX
ISBN 13: OCLC:476023575
Language: EN, FR, DE, ES & NL

Reactor Core Design for High temperature Gas cooled Reactors Book Review: