Modeling and Analysis of Thermal-hydraulic Response of Uranium- Aluminum Reactor Fuel Plates Under Transient Heatup Conditions PDF Download
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Category :
Languages : en
Pages : 19
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Book Description
A 3-D model to predict the thermal behavior of ANS (Advanced Neutron Source) fuel miniplates has been developed. Possibility of explosive boiling was considered, and it was concluded that the heating rates (existant in NSRR tests) are not large enough for this to occur. However, transient boiling effects were pronounced. Because of the complexity of transient pool boiling and the unavailability of experimental data for the situations studied, an approximation was made that predicted the data very well within the uncertainties present. If pool boiling from the miniplates had been assumed to be steady during the heating pulse, the experimental data would have been greatly overestimated. This shows the importance of considering the transient nature of heat transfer in analysis of reactivity excursion accidents. An additional contribution of this work is that it provided data on highly subcooled steady nucleate boiling from the cooling portion of the thermocouple traces.
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Category :
Languages : en
Pages : 19
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Book Description
A 3-D model to predict the thermal behavior of ANS (Advanced Neutron Source) fuel miniplates has been developed. Possibility of explosive boiling was considered, and it was concluded that the heating rates (existant in NSRR tests) are not large enough for this to occur. However, transient boiling effects were pronounced. Because of the complexity of transient pool boiling and the unavailability of experimental data for the situations studied, an approximation was made that predicted the data very well within the uncertainties present. If pool boiling from the miniplates had been assumed to be steady during the heating pulse, the experimental data would have been greatly overestimated. This shows the importance of considering the transient nature of heat transfer in analysis of reactivity excursion accidents. An additional contribution of this work is that it provided data on highly subcooled steady nucleate boiling from the cooling portion of the thermocouple traces.
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ISBN:
Category : Power resources
Languages : en
Pages : 812
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Author: Bahman Zohuri
Publisher: Springer
ISBN: 3319174347
Category : Science
Languages : en
Pages : 667
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Book Description
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
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Languages : en
Pages :
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Book Description
Small samples of aluminum-enriched uranium alloy plates submerged in room temperature water were subjected to severe nuclear transients in Treat to determine the extent of metal water reaction and to observe the physical changes that occurred. A standard SPERT 1-D type fuel plate was used for one of the tests. The extent of reaction was determined by measuring the hydrogen evolved. Metallographic examinations indicated an increase in porosity with increased energy input. Large spherical pores were formed indicating the accumulation of gas. Results are graphically shown. (N.W.R.).
Author: Jun Wang
Publisher: Frontiers Media SA
ISBN: 2889456129
Category :
Languages : en
Pages : 120
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Book Description
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.
Author: Donna Guillen
Publisher: BoD – Books on Demand
ISBN: 9535109871
Category : Technology & Engineering
Languages : en
Pages : 204
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Book Description
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.
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1132
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ISBN:
Category : Heat
Languages : en
Pages : 218
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Book Description
Author: Yu-Chih Ko (Ph. D.)
Publisher:
ISBN:
Category :
Languages : en
Pages : 290
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Book Description
The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for the MIT reactor is evolving. The objectives of this study are to benchmark the in-house computer code for the MITR, and to perform the thermal hydraulic analyses in support of the LEU design studies. The in-house multi-channel thermal-hydraulics code, MULCH-II, was developed specifically for the MITR. This code was validated against PLTEMP for steady-state analysis, and RELAP5 and temperature measurements for the loss of primary flow transient. Various fuel configurations are evaluated as part of the LEU core design optimization study. The criteria adopted for the LEU thermal hydraulics analysis for this study are the limiting safety system settings (LSSS), to prevent onset of nucleate boiling during steady-state operation, and to avoid a clad temperature excursion during the loss of flow transient. The benchmark analysis results showed that the MULCH-II code is in good agreement with other computer codes and experimental data, and hence it is used as the main tool for this study. In ranking the LEU core design options, the primary parameter is a low power peaking factor in order to increase the LSSS power and to decrease the maximum clad temperature during the transient. The LEU fuel designs with 15 to 18 plates per element, fuel thickness of 20 mils, and a hot channel factor less than 1.76 are shown to comply with these thermal-hydraulic criteria. The steady-state power can potentially be higher than 6 MW, as requested in the power upgrade submission to the Nuclear Regulatory Commission.
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1004
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