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Thermal Hydraulic Calculations To Support Increase In Operating Power In Mcclellen Nuclear Radiation Centermnrc Triga Reactor
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Book Synopsis Thermal Hydraulic Calculations to Support Increase in Operating Power in McClellen Nuclear Radiation Center(MNRC) TRIGA Reactor by :
Download or read book Thermal Hydraulic Calculations to Support Increase in Operating Power in McClellen Nuclear Radiation Center(MNRC) TRIGA Reactor written by and published by . This book was released on 1998 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The RELAP5/Mod3.1 computer program has been used to successfully perform thermal-hydraulic analyses to support the Safety Analysis for increasing the MNRC reactor from 1.0 MW to 2.0 MW. The calculation results show the reactor to have operating margin for both the fuel temperature and critical heat flux limits. The calculated maximum fuel temperature of 705 C is well below the 750 C operating limit. The critical heat flux ratio was calculated to be 2.51.
Book Synopsis Thermal-Hydraulic Analysis of Nuclear Reactors by : Bahman Zohuri
Download or read book Thermal-Hydraulic Analysis of Nuclear Reactors written by Bahman Zohuri and published by Springer. This book was released on 2015-09-09 with total page 667 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play. Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors. This book also: Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, beginning with fundamental definitions of units and dimensions, thermodynamic variables, and the Laws of Thermodynamics progressing to sections on specific applications of the Brayton and Rankine cycles for power generation and projected reactor systems design issues Reinforces fundamentals of fluid dynamics and heat transfer; thermal and hydraulic analysis of nuclear reactors, two-phase flow and boiling, compressible flow, stress analysis, and energy conversion methods Includes detailed appendices that cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties, and nuclear reactor system descriptions
Book Synopsis Nuclear Reactor Thermal Hydraulics and Other Applications by : Donna Guillen
Download or read book Nuclear Reactor Thermal Hydraulics and Other Applications written by Donna Guillen and published by BoD – Books on Demand. This book was released on 2013-02-13 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book includes contributions from researchers around the world on numerical developments and applications to predict fluid flow and heat transfer, with an emphasis on thermal hydraulics computational fluid dynamics. Our ability to simulate larger problems with greater fidelity has vastly expanded over the past decade. The collection of material presented in this book augments the ever-increasing body of knowledge concerning the important topic of thermal hydraulics. Featured topics include coolant channel analysis, thermal hydraulic transport and mixing, as well as hydrodynamics and heat transfer processes. The contents of this book will interest researchers, scientists, engineers and graduate students.
Book Synopsis Nuclear Thermal Hydraulic and Two-Phase Flow by : Jun Wang
Download or read book Nuclear Thermal Hydraulic and Two-Phase Flow written by Jun Wang and published by Frontiers Media SA. This book was released on 2018-10-11 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.
Book Synopsis Proceedings of Nuclear Thermal Hydraulics by :
Download or read book Proceedings of Nuclear Thermal Hydraulics written by and published by . This book was released on 1994 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Reactor Thermal Hydraulics by : Robert E. Masterson
Download or read book Nuclear Reactor Thermal Hydraulics written by Robert E. Masterson and published by CRC Press. This book was released on 2019-08-21 with total page 1354 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.
Book Synopsis Thermal-hydraulics in Nuclear Power Technology by : Kauo-hwa Sun
Download or read book Thermal-hydraulics in Nuclear Power Technology written by Kauo-hwa Sun and published by . This book was released on 1981 with total page 98 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Second Proceedings of Nuclear Thermal Hydraulics Annual Summer Meeting, June 3 - June 7, 1984, New Orleans by : American Nuclear Society. Thermal Hydraulics Division. Meeting
Download or read book Second Proceedings of Nuclear Thermal Hydraulics Annual Summer Meeting, June 3 - June 7, 1984, New Orleans written by American Nuclear Society. Thermal Hydraulics Division. Meeting and published by . This book was released on 1984 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors by : Francesco D'Auria
Download or read book Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors written by Francesco D'Auria and published by Elsevier. This book was released on 2024-07-29 with total page 932 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 1, Foundations and Principles includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix Covers applicable nuclear reactor safety considerations and design technology throughout
Book Synopsis Development of Thermal Hydraulic Correlations for the University of Texas at Austin TRIGA Reactor Using Computational Fluid Dynamics and In-core Measurements by : Alexander Douglas Brand
Download or read book Development of Thermal Hydraulic Correlations for the University of Texas at Austin TRIGA Reactor Using Computational Fluid Dynamics and In-core Measurements written by Alexander Douglas Brand and published by . This book was released on 2013 with total page 334 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safety is a paramount concern in the operation of training and test reactors. A major component of a reactor is the maintenance of safe thermal hydraulic operating conditions. If the temperature of the water coolant exceeds the boiling point, the heat transfer out of the fuel rods into the coolant will greatly decrease and will need to rely upon other safety feedbacks and systems to avoid an accident condition. TRIGA thermal hydraulic systems are currently modeled using a finite differencing code, TRACE/SNAP, developed by the Nuclear Regulatory Commission. While the code is currently certified, it has shortcomings that this work improves upon, notably the simplification of the more complex flow geometries by using circular pipes and a heat transfer correlation that is valid across all flow regimes observed during operation of the TRIGA. A computational fluid dynamics code, FLUENT, along with real-time thermocouple probe measurements of the channel were used to solve both of these major issues. A high resolution model of four adjacent flow channels was created to provide a numerical experimental data set for enhancing the correlations used in the TRACE model. The hot flow channel is connected to three surrounding channels where crossflow occurs causing a more complex flow pattern than the isolated single channel system used in TRACE/SNAP. To calibrate the FLUENT model, a thermocouple probe was designed and placed in the TRIGA core in the center of the flow channel. The reactor was operated over the full range of licensed power levels to obtain a fully encompassing data set of coolant temperatures. The FLUENT model was then adjusted so that the temperatures at the location of the probe in the model matched those from the experimental measurements. Based on the results from the FLUENT testing, data was extracted to develop a new heat transfer coefficient correlation and loss factor coefficient correlation due to the non-circular geometry and fuel rod end fittings for use in the TRACE/SNAP code. These adjustments were then implemented into TRACE/SNAP to improve the code for future users performing safety analysis on TRIGA reactors.
Book Synopsis Nuclear Reactor Thermal Hydraulics by : Matt Fulcher
Download or read book Nuclear Reactor Thermal Hydraulics written by Matt Fulcher and published by . This book was released on 2015-03-21 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The book discusses various applications and feasibility of thermal hydraulics in detail. This book encompasses information contributed by researchers from across the globe on numerical advancements and applications to estimate fluid flow and heat transfer, focusing on thermal hydraulics computational fluid dynamics. The capability to stimulate bigger complications with more consistency has significantly expanded over the last decade. The compilation of material described in this book enhances the ever-increasing body of knowledge regarding the crucial topic of thermal hydraulics. The primary topics covered in this book include thermal hydraulic transport and mixing, coolant channel analysis, as well as heat transfer procedures and hydrodynamics. This book will serve as a great source of reference for researchers, students, engineers and even scientists.
Book Synopsis Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors by : Francesco D'Auria
Download or read book Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors written by Francesco D'Auria and published by Elsevier. This book was released on 2024-07-29 with total page 818 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 3, Procedures and Applications includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix Covers applicable nuclear reactor safety considerations and design technology throughout
Book Synopsis Nuclear and Thermal Hydraulic Effects of Fuel Rod Bowing by : Vinod Sehgal
Download or read book Nuclear and Thermal Hydraulic Effects of Fuel Rod Bowing written by Vinod Sehgal and published by . This book was released on 1977 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors by : Ferry Roelofs
Download or read book Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors written by Ferry Roelofs and published by Woodhead Publishing. This book was released on 2018-11-30 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications
Book Synopsis Thermal-hydraulics of Nuclear Reactors by : Mati Merilo
Download or read book Thermal-hydraulics of Nuclear Reactors written by Mati Merilo and published by . This book was released on 1983 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulic Analysis of the Oregon State TRIGA Reactor Using RELAP5-3D by : Wade R. Marcum
Download or read book Thermal Hydraulic Analysis of the Oregon State TRIGA Reactor Using RELAP5-3D written by Wade R. Marcum and published by . This book was released on 2008 with total page 302 pages. Available in PDF, EPUB and Kindle. Book excerpt: Oregon State University has recently conducted a complete core conversion analysis as part of the Reduced Enrichment for Research and Test Reactors Pprogram. The goals of the thermal hydraulic analyses were to calculate natural circulation flow rates, coolant temperatures and fuel temperatures as a function of core power for both the Highly Enriched Uranium (HEU) and Low Enriched Uranium (LEU) cores; for steady state and pulsed operation, calculate peak values of fuel temperature, cladding temperature, surface heat flux as well as critical heat flux ratio (CHFR) and temperature profiles in hot channel for both the HEU and LEU cores; finally, perform accident analyses for the accident scenarios identified in the Oregon State TRIGA® Reactor (OSTR) Safety Analysis Report (SAR). RELAP5-3D Version 2.4.2 was used for all computational modeling during the thermal hydraulics analysis. This is a lumped parameter code forcing engineering assumptions to be made during the analysis. A single hot channel model's results are compared to that produced from more refined two and eight channel models in order to identify variations in thermal hydraulic characteristics as a function of spatial refinement.
Book Synopsis Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors by : Francesco D'Auria
Download or read book Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors written by Francesco D'Auria and published by Elsevier. This book was released on 2024-07-29 with total page 1012 pages. Available in PDF, EPUB and Kindle. Book excerpt: Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 2, Modelling includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix Covers applicable nuclear reactor safety considerations and design technology throughout
