Strategic Need For A Multi Purpose Thermal Hydraulic Loop For Support Of Advanced Reactor Technologies
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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.
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.
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.
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment
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Author : Jyeshtharaj Joshi
language : en
Publisher: Woodhead Publishing
Release Date : 2019-06-15
Advances Of Computational Fluid Dynamics In Nuclear Reactor Design And Safety Assessment written by Jyeshtharaj Joshi and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2019-06-15 with Science categories.
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization
Development Of A Multi Loop Flow And Heat Transfer Facility For Advanced Nuclear Reactor Thermal Hydraulic And Hybrid Energy System Studies
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Author :
language : en
Publisher:
Release Date : 2001
Development Of A Multi Loop Flow And Heat Transfer Facility For Advanced Nuclear Reactor Thermal Hydraulic And Hybrid Energy System Studies 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.
A new high-temperature multi-fluid, multi-loop test facility for advanced nuclear applications is under development at the Idaho National Laboratory. The facility will include three flow loops: high-temperature helium, molten salt, and steam/water. Molten salts have been identified as excellent candidate heat transport fluids for primary or secondary coolant loops, supporting advanced high temperature and small modular reactors (SMRs). Details of some of the design aspects and challenges of this facility, which is currently in the conceptual design phase, are discussed. A preliminary design configuration will be presented, with the required characteristics of the various components. The loop will utilize advanced high-temperature compact printed-circuit heat exchangers (PCHEs) operating at prototypic intermediate heat exchanger (IHX) conditions. The initial configuration will include a high-temperature (750°C), high-pressure (7 MPa) helium loop thermally integrated with a molten fluoride salt (KF-ZrF4) flow loop operating at low pressure (0.2 MPa) at a temperature of ~450°C. Experiment design challenges include identification of suitable materials and components that will withstand the required loop operating conditions. Corrosion and high temperature creep behavior are major considerations. The facility will include a thermal energy storage capability designed to support scaled process heat delivery for a variety of hybrid energy systems and grid stabilization strategies. Experimental results obtained from this research will also provide important data for code ve.
Nuclear Thermal Hydraulic And Two Phase Flow
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Author : Jun Wang
language : en
Publisher: Frontiers Media SA
Release Date : 2018-10-11
Nuclear Thermal Hydraulic And Two Phase Flow written by Jun Wang and has been published by Frontiers Media SA this book supported file pdf, txt, epub, kindle and other format this book has been release on 2018-10-11 with categories.
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.
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
The Thermal Hydraulics Of A Boiling Water Nuclear Reactor
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Author : Richard T. Lahey
language : en
Publisher:
Release Date : 1977
The Thermal Hydraulics Of A Boiling Water Nuclear Reactor written by Richard T. Lahey and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1977 with Boiling water reactors categories.
A monograph presenting an up-to-date overview of the thermal-hydraulic technology that underlies the design, operation, and safety assessment of boiling water nuclear reactors (BWRs), which represent a large fraction of the world's installed nuclear power capacity. Some important new material on pressure suppression containment technology has been added to this edition in order to provide readers with a more comprehensive understanding of BWR power plants. For experienced and entry-level workers in the field of nuclear energy, as well as for students of nuclear engineering. Annotation copyright by Book News, Inc., Portland, OR
Safety Analysis For A Fuel Qualification Test With Supercritical Water
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Author : Raqué, Manuel
language : en
Publisher: KIT Scientific Publishing
Release Date : 2015-01-07
Safety Analysis For A Fuel Qualification Test With Supercritical Water written by Raqué, Manuel and has been published by KIT Scientific Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2015-01-07 with categories.
1978 Erda Authorization
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Author : United States. Congress. House. Committee on Science and Technology
language : en
Publisher:
Release Date : 1977
1978 Erda Authorization written by United States. Congress. House. Committee on Science and Technology and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1977 with Fossil fuels categories.