Advances in High Temperature Gas Cooled Reactor Fuel Technology PDF Download
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Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639
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Book Description
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.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201253101
Category : Business & Economics
Languages : en
Pages : 639
Get Book Here
Book Description
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.
Author: Tetsuaki Takeda
Publisher: Academic Press
ISBN: 012821032X
Category : Business & Economics
Languages : en
Pages : 478
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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.
Author: Kazuo Minato
Publisher:
ISBN:
Category :
Languages : ja
Pages : 25
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Book Description
Author:
Publisher:
ISBN:
Category : Gas coded reactors
Languages : en
Pages : 962
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Book Description
Author: United States. Congress. House. Committee on Science and Technology. Subcommittee on Energy Research and Production
Publisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 216
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Book Description
Author: Hitesh Bindra
Publisher: Academic Press
ISBN: 0128139765
Category : Science
Languages : en
Pages : 300
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Book Description
Storage and Hybridization of Nuclear Energy: Techno-economic Integration of Renewable and Nuclear Energy provides a unique analysis of the storage and hybridization of nuclear and renewable energy. Editor Bindra and his team of expert contributors present various global methodologies to obtain the techno-economic feasibility of the integration of storage or hybrid cycles in nuclear power plants. Aimed at those studying, researching and working in the nuclear engineering field, this book offers nuclear reactor technology vendors, nuclear utilities workers and regulatory commissioners a very unique resource on how to access reliable, flexible and clean energy from variable-generation. Presents a unique view on the technologies and systems available to integrate renewables and nuclear energy Provides insights into the different methodologies and technologies currently available for the storage of energy Includes case studies from well-known experts working on specific integration concepts around the world
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309043956
Category : Science
Languages : en
Pages : 234
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Book Description
The construction of nuclear power plants in the United States is stopping, as regulators, reactor manufacturers, and operators sort out a host of technical and institutional problems. This volume summarizes the status of nuclear power, analyzes the obstacles to resumption of construction of nuclear plants, and describes and evaluates the technological alternatives for safer, more economical reactors. Topics covered include: Institutional issues-including regulatory practices at the federal and state levels, the growing trends toward greater competition in the generation of electricity, and nuclear and nonnuclear generation options. Critical evaluation of advanced reactors-covering attributes such as cost, construction time, safety, development status, and fuel cycles. Finally, three alternative federal research and development programs are presented.
Author: Cihang Lu
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Highly innovative nuclear reactor technologies have the potential to meet the global energy demand while reducing carbon emissions. Generation IV reactors, with advances in safety, reliability, sustainability and economic benefits, are currently being investigated. The high-temperature gas-cooled reactor (HTGR), moderated by graphite and cooled by helium, has the highest technology readiness level compared to the other Generation IV reactor designs.Conventional HTGR fuel consists of TRistructural ISOtropic (TRISO) coated fuel particles embedded in a graphite matrix. Several historic HTGRs fueled with conventional fuel have been constructed and operated, including the Peach Bottom Unit No.1 reactor operated in Pennsylvania and the Fort St. Vrain reactor that was operated in Colorado.The FCM fuel consists of TRistructural ISOtropic (TRISO) coated fuel particles embedded in a silicon carbide (SiC) matrix. Compared to the conventional HTGR fuel, the FCM fuel could potentially enhance the safety of the reactor due to the numerous advantages provided by the SiC matrix. The FCM fuel features enhanced ability to retain fission products. The FCM fuel exhibits a greater stability under irradiation and less swelling after irradiation. Moreover, the FCM fuel has better mechanical characteristics and would be less sensitive to physical disturbances. The FCM fuel has higher oxidation resistance and would suffer less damage in air-ingress accidents. The SiC matrix may also increase the proliferation resistance of the FCM fuel.However, due to the replacement of the graphite matrix in the conventional HTGR fuel, the FCM fuel hardens the neutron spectrum in the reactor core. This may further cause economic penalties of an FCM-fueled HTGR as well as a higher fuel temperature which jeopardizes the core safety.This dissertation proved the viability of FCM-fueled HTGRs by answering the following six questions based on analysis of experimental data as well as neutronics and thermal-hydraulics numerical calculations:(1) What are the key changes in fuel cycle performance and fuel cost of HTGRs with the FCM fuel?(2) What is the potential impact of the FCM fuel on reactor performance and safety characteristics of HTGRs?(3) How does the FCM fuel impact anticipated transients and design-basis accidents?(4) What are the most important parameters for each of the design-basis accidents and their sensitivities to the maximum fuel temperature?(5) What is the kinetics of the annealing process of neutron-irradiated SiC?(6) Does the irradiation defect annealing process of SiC significantly impact fuel temperature during design-basis accidents?The reference HTGR core configuration considered was the General Atomics designed 350-MWt prismatic mHTGR which has a prismatic block configuration similar to the Fort St. Vrain reactor.In this dissertation, I identified three FCM fuel options which are able to maintain the fuel cycle length of the reference core. However, because of the higher natural resource requirement, the FCM fuel cycle cost could be up to 74% more expensive than the conventional HTGR fuel. The impact of the FCM fuel on the other parameters which are important to the core safety, including decay power, reactivity temperature coefficients and control rod worth, is minor. I investigated three typical design-basis accidents of the HTGRs, including the pressurized loss of forced cooling accident, the depressurized loss of forced cooling accident and the control rod withdrawal accident. The maximum fuel temperature of an FCM-fuel core could be up to 65 K higher than that of the reference core during normal operating conditions, and the peak maximum fuel temperature of an FCM-fuel core could be up to 55 K higher than that of the reference core during those design-basis accidents. I also studied the sensitivity of the maximum fuel temperature to various parameters of interest during different operating conditions and identified the steady-state power distribution to have the largest impact on the peak maximum fuel temperature during the design-basis accidents. By analyzing acquired experimental data, I elucidated information on the kinetics of the SiC annealing process. I further estimated the maximum possible impact of the SiC annealing process on the maximum fuel temperature of FCM-fueled HTGRs during design-basis accidents based on conservative assumptions. The SiC annealing process would at most increase the peak maximum fuel temperature of an FCM-fueled HTGR by 40 K.According to the calculations conducted, the increase of the maximum fuel temperature caused by the use of the FCM fuel in HTGRs would not exceed 100 K which is minor compared to the maximum fuel temperature of around 1200 K in the reference core during normal operating conditions. Therefore, the use of the FCM fuel in HTGRs is viable.Additionally, by comparing calculation results with experimental data, I demonstrated the validity of the system analysis code RELAP5-3D to conduct thermal-hydraulics calculations of transients in HTGRs.
Author: Shengyao Jiang
Publisher: Springer Nature
ISBN: 9811595658
Category : Science
Languages : en
Pages : 510
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Book Description
This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.
Author: Gilbert Melese
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444
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Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
