Scaling Approach and Thermal-hydraulic Analysis in the Reactor Cavity Cooling System of a High Temperature Gas-cooled Reactor and Thermal-jet Mixing in a Sodium Fast Reactor PDF Download
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Author: Olumuyiwa A. Omotowa
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 502
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Book Description
Author: Olumuyiwa A. Omotowa
Publisher:
ISBN:
Category : Fast reactors
Languages : en
Pages : 502
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Book Description
Author: Francesco D'Auria
Publisher: Woodhead Publishing
ISBN: 0081006799
Category : Technology & Engineering
Languages : en
Pages : 1200
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Book Description
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
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 484
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Book Description
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
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Book Description
Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.
Author: S. Sherman
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The US Department of Energy is investigating the use of high-temperature nuclear reactors to produce hydrogen using either thermochemical cycles or high-temperature electrolysis. Although the hydrogen production processes are in an early stage of development, coupling either of these processes to the high-temperature reactor requires both efficient heat transfer and adequate separation of the facilities to assure that off-normal events in the production facility do not impact the nuclear power plant. An intermediate heat transport loop will be required to separate the operations and safety functions of the nuclear and hydrogen plants. A next generation high-temperature reactor could be envisioned as a single-purpose facility that produces hydrogen or a dual-purpose facility that produces hydrogen and electricity. Early plants, such as the proposed Next Generation Nuclear Plant (NGNP), may be dual-purpose facilities that demonstrate both hydrogen and efficient electrical generation. Later plants could be single-purpose facilities. At this stage of development, both single- and dual-purpose facilities need to be understood. A number of possible configurations for a system that transfers heat between the nuclear reactor and the hydrogen and/or electrical generation plants were identified. These configurations included both direct and indirect cycles for the production of electricity. Both helium and liquid salts were considered as the working fluid in the intermediate heat transport loop. Methods were developed toperform thermal-hydraulic and cycle-efficiency evaluations of the different configurations and coolants. The thermal-hydraulic evaluations estimated the sizes of various components in the intermediate heat transport loop for the different configurations. The relative sizes of components provide a relative indication of the capital cost associated with the various configurations. Estimates of the overall cycle efficiency of the various configurations were also determined. The evaluations determined which configurations and coolants are the most promising from thermalhydraulic and efficiency points of view.
Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856071
Category : Business & Economics
Languages : en
Pages : 932
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Book Description
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
Author: IAEA
Publisher:
ISBN: 9789201136022
Category :
Languages : en
Pages : 277
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Book Description
Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 032385611X
Category : Technology & Engineering
Languages : en
Pages : 1012
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Book Description
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
Author: Liaqat Ali
Publisher:
ISBN:
Category :
Languages : tr
Pages :
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Book Description
The importance of the present analysis stems from the interest to arrest a severe reactor accident, resulting in partial or full degradation/melting of the core assembly. In such acase the molten material will relocate in to the lower head of the pressure vessel, after passing through a series of molten and refrozen states. Reactor Pressure V essel (RPV),which is the last barrier against the release of the radioactivity to the containment, is thermally attacked by the corium. Uranium based reactor fuel and tission products from the bumed fuel are present in the corium. Fission products ' decay with their respective half lives, introduces an intemal heat source, which is more or less uniform within the molten mass. Due to high melting point of the ceramic fuel constituents and the radioactivity associated with tission products, the system becomes unmanageable experimentally. Thus leaving numerical simulation only viable tool to look for thermal hydraulic phenomenon occurring inside the corium pool formed in the RPV lower head.The understanding of the flow and heat transfer characteristics associated with the"problem can possibly lead to accident management sheme, thus reducing the risk of release of radioactivity to the containment and eventually to the atmosphere.Present analysis was started with the study of buoyant flow in a discretely heated squa recavity follow Rayleigh numbers. This problem was selected due to its importance in the Computational Fluid Dynamics literature as a benchmark solution. A very good agreement was obtained between the results from present software and those from the open literature.Secondly natural convection flow in an intemally heated square cavity was analysedusing the present software for low Ra numbers. Results were compared with published results of other researchers. Both results showed a very good agreement.As scaling for high Ra number with intemal heat generation was not available in the open literature, so a scaling was developed for such a case. These scaling and obtained results were published.Reactor pressure vessel has a thick stainless steel wall, thus introducing a conjugate problem. For the analysis of the conjugate problem ghost nodes induction method was adopted. Then the results obtained for an intemally heated square cavity having thick conducting walls were presented in a paper .Corium is a low Pr number fluid, so the analysis of the buoyant flow in corium contained in a thick walled square cavity was performed and results were presented as a conference paper.To understand the effect of thick conducting wall enclosing a semi-circular cavity from bottom, analysis was carried out for an intemally heated semi-circular cavity. These results were compared with a semi-circular cavity with isothermal walls and the difference was analysed.Due to the peculiar layout of the hemi-spherical RPV lower head, only half of the cavitywas analysed. The results indicated that although average Nusselt number was comparable but the non-symmetric nature of the flow could not be obtained. Therefore,the semi-circular cavity was selected for final analysis.Final analysis geometry was selected to represent actual situation as closely as possible.As temperature in the corium pool will reach 3 500 K, so radiation heat transfer fromthe pool surface was included in the analysis. The three heat transfer mechanisms,conduction, convection and radiation, are present in the analysis. Only radiative heattransfer from the pool surface and associated radiating surfaces was included.Results show that the temperatures in the pool are well stratified with convection dominated region confined to upper part of the pool. Effect of pool surface emissivityand parameter LlT/Tw has also been analysed in detail. Ra number range of 3.2xl07 to3.2xlO13 has been studied with last value at the margin of initiation of turbulent flow.Results also indicate that most probable point of failure of the RPV wall is close to thepoint of contact of the free surface with RPV wall. Also the stagnation point will neverbe in danger from thermal attack of the contained corium.Thus a detail analysis of the present problem has been performed. It is hoped that this analysis will greatly increase the understanding of the thermal hydraulic phenomenon associated with the present problem.in the following chapters details of the computational work performed during present doctoral dissertation has been presented. In chapter 2, goveming equations for different cases analysed are presented in full dimensional form together with dimension less equivalents. Also, scale analysis for high Rayleigh number buoyant flow has been outlined. Chapter 3 includes the summary of grid layout employed for the analysis andderivation of pressure and pressure correction equations. Organisation of software and numerical methodology adopted for the present analysis has been listed in chapter 4. Aflow diagram of the algorithm is also included in chapter 4. Chapter 5 has two mainparts, in first part benchmark results are presented while in second part results and conclusions conceming the present analysis are given.
Author: Francesco D'Auria
Publisher: Elsevier
ISBN: 0323856098
Category : Technology & Engineering
Languages : en
Pages : 818
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Book Description
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
