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Author: Chang Oh
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The Idaho National Engineering and EnvironmentalLaboratory (INEEL) is investigating a Brayton cycle efficiencyimprovement on a high temperature gas-cooled reactor (HTGR)as part of Generation-IV nuclear engineering research initiative. In this project, we are investigating helium Brayton cyclesfor the secondary side of an indirect energy conversion system. Ultimately we will investigate the improvement of the Braytoncycle using other fluids, such as supercritical carbon dioxide. Prior to the cycle improvement study, we established a numberof baseline cases for the helium indirect Brayton cycle. Thesecases look at both single-shaft and multiple-shaftturbomachinary. The baseline cases are based on a 250 MWthermal pebble bed HTGR. The results from this study areapplicable to other reactor concepts such as a very hightemperature gas-cooled reactor (VHTR), fast gas-cooled reactor(FGR), supercritical water reactor (SWR), and others. In this study, we are using the HYSYS computer code foroptimization of the helium Brayton cycle. Besides the HYSYSprocess optimization, we performed parametric study to see theeffect of important parameters on the cycle efficiency. Forthese parametric calculations, we use a cycle efficiency modelthat was developed based on the Visual Basic computerlanguage. As a part of this study we are currently investigatedsingle-shaft vs. multiple shaft arrangement for cycle efficiencyand comparison, which will be published in the next paper. The ultimate goal of this study is to use supercriticalcarbon dioxide for the HTGR power conversion loop in orderto improve the cycle efficiency to values great than that of thehelium Brayton cycle. This paper includes preliminary calculations of the steadystate overall Brayton cycle efficiency based on the pebble bedreactor reference design (helium used as the working fluid) andcompares those results with an initial calculation of a CO2Brayton cycle.
Author: Chang Oh
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The Idaho National Engineering and EnvironmentalLaboratory (INEEL) is investigating a Brayton cycle efficiencyimprovement on a high temperature gas-cooled reactor (HTGR)as part of Generation-IV nuclear engineering research initiative. In this project, we are investigating helium Brayton cyclesfor the secondary side of an indirect energy conversion system. Ultimately we will investigate the improvement of the Braytoncycle using other fluids, such as supercritical carbon dioxide. Prior to the cycle improvement study, we established a numberof baseline cases for the helium indirect Brayton cycle. Thesecases look at both single-shaft and multiple-shaftturbomachinary. The baseline cases are based on a 250 MWthermal pebble bed HTGR. The results from this study areapplicable to other reactor concepts such as a very hightemperature gas-cooled reactor (VHTR), fast gas-cooled reactor(FGR), supercritical water reactor (SWR), and others. In this study, we are using the HYSYS computer code foroptimization of the helium Brayton cycle. Besides the HYSYSprocess optimization, we performed parametric study to see theeffect of important parameters on the cycle efficiency. Forthese parametric calculations, we use a cycle efficiency modelthat was developed based on the Visual Basic computerlanguage. As a part of this study we are currently investigatedsingle-shaft vs. multiple shaft arrangement for cycle efficiencyand comparison, which will be published in the next paper. The ultimate goal of this study is to use supercriticalcarbon dioxide for the HTGR power conversion loop in orderto improve the cycle efficiency to values great than that of thehelium Brayton cycle. This paper includes preliminary calculations of the steadystate overall Brayton cycle efficiency based on the pebble bedreactor reference design (helium used as the working fluid) andcompares those results with an initial calculation of a CO2Brayton cycle.
Author: C. L. Whitmarsh
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 36
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 34
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This report outlines the thermodynamics of a supercritical carbon dioxide (sCO2) recompression closed Brayton cycle (RCBC) coupled to a Helium-cooled nuclear reactor. The baseline reactor design for the study is the AREVA High Temperature Gas-Cooled Reactor (HTGR). Using the AREVA HTGR nominal operating parameters, an initial thermodynamic study was performed using Sandia's deterministic RCBC analysis program. Utilizing the output of the RCBC thermodynamic analysis, preliminary values of reactor power and of Helium flow rate through the reactor were calculated in Sandia's HelCO2 code. Some research regarding materials requirements was then conducted to determine aspects of corrosion related to both Helium and to sCO2, as well as some mechanical considerations for pressures and temperatures that will be seen by the piping and other components. This analysis resulted in a list of materials-related research items that need to be conducted in the future. A short assessment of dry heat rejection advantages of sCO2> Brayton cycles was also included. This assessment lists some items that should be investigated in the future to better understand how sCO2 Brayton cycles and nuclear can maximally contribute to optimizing the water efficiency of carbon free power generation.
Author: Albert J. Juhasz
Publisher:
ISBN:
Category : Nuclear propulsion
Languages : en
Pages : 16
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Author: W. Z. Prickett
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 50
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Author: C. L. Whitmarsh
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 52
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 93
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The primary metric for the viability of these next generation nuclear power plants will be the cost of generated electricity. One important component in achieving these objectives is the development of power conversion technologies that maximize the electrical power output of these advanced reactors for a given thermal power. More efficient power conversion systems can directly reduce the cost of nuclear generated electricity and therefore advanced power conversion cycle research is an important area of investigation for the Generation IV Program. Brayton cycles using inert or other gas working fluids, have the potential to take advantage of the higher outlet temperature range of Generation IV systems and allow substantial increases in nuclear power conversion efficiency, and potentially reductions in power conversion system capital costs compared to the steam Rankine cycle used in current light water reactors. For the Very High Temperature Reactor (VHTR), Helium Brayton cycles which can operate in the 900 to 950 C range have been the focus of power conversion research. Previous Generation IV studies examined several options for He Brayton cycles that could increase efficiency with acceptable capital cost implications. At these high outlet temperatures, Interstage Heating and Cooling (IHC) was shown to provide significant efficiency improvement (a few to 12%) but required increased system complexity and therefore had potential for increased costs. These scoping studies identified the potential for increased efficiency, but a more detailed analysis of the turbomachinery and heat exchanger sizes and costs was needed to determine whether this approach could be cost effective. The purpose of this study is to examine the turbomachinery and heat exchanger implications of interstage heating and cooling configurations. In general, this analysis illustrates that these engineering considerations introduce new constraints to the design of IHC systems that may require different power conversion configurations to take advantage of the possible efficiency improvement. Very high efficiency gains can be achieved with the IHC approach, but this can require large low pressure turbomachinery or heat exchanger components, whose cost may mitigate the efficiency gain. One stage of interstage cooling is almost always cost effective, but careful optimization of system characteristics is needed for more complex configurations. This report summarizes the primary factors that must be considered in evaluating this approach to more efficient cycles, and the results of the engineering analysis performed to explore these options for Generation IV high temperature reactors.
Author: Igor Pioro
Publisher: Woodhead Publishing
ISBN: 0128226536
Category : Technology & Engineering
Languages : en
Pages : 1112
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Book Description
Handbook of Generation IV Nuclear Reactors, Second Edition is a fully revised and updated comprehensive resource on the latest research and advances in generation IV nuclear reactor concepts. Editor Igor Pioro and his team of expert contributors have updated every chapter to reflect advances in the field since the first edition published in 2016. The book teaches the reader about available technologies, future prospects and the feasibility of each concept presented, equipping them users with a strong skillset which they can apply to their own work and research. Provides a fully updated, revised and comprehensive handbook dedicated entirely to generation IV nuclear reactors Includes new trends and developments since the first publication, as well as brand new case studies and appendices Covers the latest research, developments and design information surrounding generation IV nuclear reactors
Author: Chang Oh
Publisher:
ISBN:
Category :
Languages : en
Pages :
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The US Department of Energy is investigating the use of high-temperature gas-cooled reactors (HTGR) [Oh,2005] to produce electricity and hydrogen. In anticipation of the design, development and procurement of an advanced power conversion system for HTGR, this study was initiated to identify the major design and technology options and their tradeoffs in the evaluation of power conversion system (PCS) options to support future research and procurement decisions. These PCS technology options affect cycle efficiency, capital cost, system reliability and maintainability and technical risk, and therefore the cost of electricity from Generation IV systems. In this study, we investigated the effect of interstage cooling in the PCS and present some results.
Author: Arthur J. Glassman
Publisher:
ISBN:
Category : Brayton cycle
Languages : en
Pages : 32
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