Multi Purpose Thermal Hydraulic Loop
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Multi Purpose Thermal Hydraulic Loop
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Author :
language : en
Publisher:
Release Date : 2001
Multi Purpose Thermal Hydraulic Loop written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2001 with categories.
Effective and robust high temperature heat transfer systems are fundamental to the successful deployment of advanced reactors for both power generation and non-electric applications. Plant designs often include an intermediate heat transfer loop (IHTL) with heat exchangers at either end to deliver thermal energy to the application while providing isolation of the primary reactor system. In order to address technical feasibility concerns and challenges a new high-temperature multi-fluid, multi-loop test facility "Advanced Reactor Technology Integral System Test facility" (ARTIST) is under development at the Idaho National Laboratory. The facility will include three flow loops: high-temperature helium, molten salt, and steam/water. Details of some of the design aspects and challenges of this facility, which is currently in the conceptual design phase, are discussed.
Strategic Need For A Multi Purpose Thermal Hydraulic Loop For Support Of Advanced Reactor Technologies
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Author :
language : en
Publisher:
Release Date : 2014
Strategic Need For A Multi Purpose Thermal Hydraulic Loop For Support Of Advanced Reactor Technologies written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2014 with categories.
This report presents a conceptual design for a new high-temperature multi fluid, multi loop test facility for the INL to support thermal hydraulic, materials, and thermal energy storage research for nuclear and nuclear-hybrid applications. In its initial configuration, the facility will include a high-temperature helium loop, a liquid salt loop, and a hot water/steam loop. The three loops will be thermally coupled through an intermediate heat exchanger (IHX) and a secondary heat exchanger (SHX). Research topics to be addressed with this facility include the characterization and performance evaluation of candidate compact heat exchangers such as printed circuit heat exchangers (PCHEs) at prototypical operating conditions, flow and heat transfer issues related to core thermal hydraulics in advanced helium-cooled and salt-cooled reactors, and evaluation of corrosion behavior of new cladding materials and accident-tolerant fuels for LWRs at prototypical conditions. Based on its relevance to advanced reactor systems, the new facility has been named the Advanced Reactor Technology Integral System Test (ARTIST) facility. Research performed in this facility will advance the state of the art and technology readiness level of high temperature intermediate heat exchangers (IHXs) for nuclear applications while establishing the INL as a center of excellence for the development and certification of this technology. The thermal energy storage capability will support research and demonstration activities related to process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will assist in development of reliable predictive models for thermal hydraulic design and safety codes over the range of expected advanced reactor operating conditions. Proposed/existing IHX heat transfer and friction correlations and criteria will be assessed with information on materials compatibility and instrumentation needs. The experimental database will guide development of appropriate predictive methods and be available for code verification and validation (V & V) related to these systems.
Thermal Hydraulics For Space Power Propulsion And Thermal Management System Design
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Author : William J. Krotiuk
language : en
Publisher: AIAA
Release Date : 1990
Thermal Hydraulics For Space Power Propulsion And Thermal Management System Design written by William J. Krotiuk and has been published by AIAA this book supported file pdf, txt, epub, kindle and other format this book has been release on 1990 with Space vehicles categories.
Numerical Modeling Of A Thermal Hydraulic Loop And Test Section Design For Heat Transfer Studies In Supercritical Fluids
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Author : Daniel Matthew McGuire
language : en
Publisher:
Release Date : 2011
Numerical Modeling Of A Thermal Hydraulic Loop And Test Section Design For Heat Transfer Studies In Supercritical Fluids written by Daniel Matthew McGuire and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2011 with Force and energy categories.
Conceptual Design Of A Thermal Hydraulic Loop For Multiple Test Geometries At Supercritical Conditions Named Supercritical Phenomena Experimental Test Apparatus Speta
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Author : Adepoju Adenariwo
language : en
Publisher:
Release Date : 2012
Conceptual Design Of A Thermal Hydraulic Loop For Multiple Test Geometries At Supercritical Conditions Named Supercritical Phenomena Experimental Test Apparatus Speta written by Adepoju Adenariwo and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with categories.
Nuclear Systems Volume Ii
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Author : Neil E. Todreas
language : en
Publisher: CRC Press
Release Date : 2021-12-13
Nuclear Systems Volume Ii written by Neil E. Todreas and has been published by CRC Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2021-12-13 with Science categories.
Discusses fundamental ideas for various modeling approaches for the macro- and micro-scale flow conditions in the reactor. Covers specific design considerations, such as natural convection and core reliability. Enables the reader to better understand the importance of safety considerations in thermal engineering and analysis of a modern nuclear plant. Features end-of-chapter problems. Includes a Solutions Manual for adopting instructors.
Nuclear Reactor Thermal Hydraulics
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Author : Robert E. Masterson
language : en
Publisher: CRC Press
Release Date : 2019-08-21
Nuclear Reactor Thermal Hydraulics written by Robert E. Masterson and has been published by CRC Press this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-08-21 with Science categories.
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.
Thermal Hydraulic Analysis Of Nuclear Reactors
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Author : Bahman Zohuri
language : en
Publisher: Springer
Release Date : 2017-05-23
Thermal Hydraulic Analysis Of Nuclear Reactors written by Bahman Zohuri and has been published by Springer this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017-05-23 with Technology & Engineering categories.
This revised 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. The book begins 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. 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. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. 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.
Thermal Hydraulics Of Water Cooled Nuclear Reactors
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Author : Francesco D'Auria
language : en
Publisher: Woodhead Publishing
Release Date : 2017-05-18
Thermal Hydraulics Of Water Cooled Nuclear Reactors written by Francesco D'Auria and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017-05-18 with Technology & Engineering categories.
Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
Experimental Thermal Hydraulic Study Of A Supercritical Co2 Natural Circulation Loop
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Author : Javad Mahmoudi
language : en
Publisher:
Release Date : 2014
Experimental Thermal Hydraulic Study Of A Supercritical Co2 Natural Circulation Loop written by Javad Mahmoudi and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2014 with categories.
Supercritical CO2 -- Natural Circulation Loop -- Thermal-hydraulics -- Friction-Factor.