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Single And Two Phase Flow Modeling For Coupled Neutronics
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Book Synopsis Single-phase, Two-phase and Supercritical Natural Circulation Systems by : Pallippattu Krishnan Vijayan
Download or read book Single-phase, Two-phase and Supercritical Natural Circulation Systems written by Pallippattu Krishnan Vijayan and published by Woodhead Publishing. This book was released on 2019-06-19 with total page 651 pages. Available in PDF, EPUB and Kindle. Book excerpt: Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation systems. This book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and parallel channel systems. Each chapter begins with an introduction to the circulation system before discussing each element in detail and analyzing its effect on the performance of the system. The book also presents thermosyphon heat transport devices in nuclear and other industrial plants, a common information need for students and researchers alike. This book is invaluable for engineers, designers, operators and consultants in nuclear, mechanical, electrical and chemical disciplines. - Presents single-phase, two-phase and supercritical natural circulation systems together in one resource to fill an existing knowledge gap - Guides the reader through relevant processes, such as designing, analyzing and generating stability maps and natural circulation loops, calculating heat transport capabilities, and maintaining natural circulation system operations - Includes global case studies and examples to increase understanding, along with important IAEA standards and procedures
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.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Modelling of Nuclear Reactor Multi-physics by : Christophe Demazière
Download or read book Modelling of Nuclear Reactor Multi-physics written by Christophe Demazière and published by Academic Press. This book was released on 2019-11-19 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. - Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference - Analyses the emerging area of multi-physics and multi-scale reactor modelling - Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding
Book Synopsis Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference by : P. F. Peterson
Download or read book Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference written by P. F. Peterson and published by . This book was released on 1993 with total page 778 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs by : Masahiro Furuya
Download or read book Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs written by Masahiro Furuya and published by IOS Press. This book was released on 2006 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt: 20% of the Nuclear Power Plants are known as Boiling Water Reactors (BWRs). These BWRs have pumps that cool their reactor. In the design of new BWRs, ways to cool the core by a natural circulation flow, without pumps, also called natural circulation BWRs, are being considered. In these new systems, a chimney is installed on top of the core to increase natural circulation flow. A possible disadvantage of natural circulation BWRs might be their susceptibility to instabilities, which could then lead to both flow and power oscillations. The stability features of both natural circulation and forced circulation BWRs have been investigated thoroughly, using dedicated experimental setups, analytical models and numerical codes. We distinguish between pure thermal-hydraulic stability - where the fission power is assumed to be constant - and coupled thermalhydraulic-neutronic stability - where the two-phase mixture in the core influences the fission chain reaction...
Book Synopsis Fractional-Order Models for Nuclear Reactor Analysis by : Gilberto Espinosa Paredes
Download or read book Fractional-Order Models for Nuclear Reactor Analysis written by Gilberto Espinosa Paredes and published by Woodhead Publishing. This book was released on 2020-10-22 with total page 404 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fractional-Order Models for Nuclear Reactor Analysis presents fractional modeling issues in the context of anomalous diffusion processes in an accessible and practical way. The book emphasizes the importance of non-Fickian diffusion in heterogeneous systems as the core of the nuclear reactor, as well as different variations of diffusion processes in nuclear reactors which are presented to establish the importance of nuclear and thermohydraulic phenomena and the physical side effects of feedback. In addition, the book analyzes core issues in fractional modeling in nuclear reactors surrounding phenomenological description and important analytical sub-diffusive processes in the transport neutron. Users will find the most innovative modeling techniques of nuclear reactors using operator differentials of fractional order and applications in nuclear design and reactor dynamics. Proposed methods are tested with Boltzmann equations and non-linear order models alongside real data from nuclear power plants, making this a valuable resource for nuclear professionals, researchers and graduate students, as well as those working in nuclear research centers with expertise in mathematical modeling, physics and control. - Presents and analyzes a new paradigm of nuclear reactor phenomena with fractional modeling - Considers principles of fractional calculation, methods of solving differential equations of fractional order, and their applications - Includes methodologies of linear and nonlinear analysis, along with design and dynamic analyses
Download or read book Nuclear Power written by Pavel Tsvetkov and published by BoD – Books on Demand. This book was released on 2011-09-06 with total page 208 pages. Available in PDF, EPUB and Kindle. Book excerpt: At the onset of the 21st century, we are searching for reliable and sustainable energy sources that have a potential to support growing economies developing at accelerated growth rates, technology advances improving quality of life and becoming available to larger and larger populations. The quest for robust sustainable energy supplies meeting the above constraints leads us to the nuclear power technology. Today's nuclear reactors are safe and highly efficient energy systems that offer electricity and a multitude of co-generation energy products ranging from potable water to heat for industrial applications. Catastrophic earthquake and tsunami events in Japan resulted in the nuclear accident that forced us to rethink our approach to nuclear safety, requirements and facilitated growing interests in designs, which can withstand natural disasters and avoid catastrophic consequences. This book is one in a series of books on nuclear power published by InTech. It consists of ten chapters on system simulations and operational aspects. Our book does not aim at a complete coverage or a broad range. Instead, the included chapters shine light at existing challenges, solutions and approaches. Authors hope to share ideas and findings so that new ideas and directions can potentially be developed focusing on operational characteristics of nuclear power plants. The consistent thread throughout all chapters is the "system-thinking" approach synthesizing provided information and ideas. The book targets everyone with interests in system simulations and nuclear power operational aspects as its potential readership groups - students, researchers and practitioners.
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 Two-Phase Flow, Boiling, and Condensation by : S. Mostafa Ghiaasiaan
Download or read book Two-Phase Flow, Boiling, and Condensation written by S. Mostafa Ghiaasiaan and published by Cambridge University Press. This book was released on 2014-08-07 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text is an introduction to gas-liquid two-phase flow, boiling and condensation for graduate students, professionals, and researchers in mechanical, nuclear, and chemical engineering. The book provides a balanced coverage of two-phase flow and phase change fundamentals, well-established art and science dealing with conventional systems, and the rapidly developing areas of microchannel flow and heat transfer. It is based on the author's more than 15 years of teaching experience. Instructors teaching multiphase flow have had to rely on a multitude of books and reference materials. This book remedies that problem by covering all the topics that are essential for a graduate first course. Among the important areas that are discussed in the book, and are not adequately covered by virtually all the available textbooks, are: two-phase flow model conservation equations and their numerical solution; condensation with and without noncondensables; and two-phase flow, boiling, and condensation in mini and microchannels.
Book Synopsis Anticipated and Abnormal Plant Transients in Light Water Reactors by : Pamela Lassahn
Download or read book Anticipated and Abnormal Plant Transients in Light Water Reactors written by Pamela Lassahn and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 725 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypo thetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and contain ment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs. " For the topic of anticipated and abnormal plant transients, how ever, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodolo gies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979. The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant.
Book Synopsis Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment by : Jyeshtharaj Joshi
Download or read book Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment written by Jyeshtharaj Joshi and published by Woodhead Publishing. This book was released on 2019-06-09 with total page 890 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Federal Software Exchange Catalog by :
Download or read book Federal Software Exchange Catalog written by and published by . This book was released on 1986 with total page 714 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the International Topical Meeting Advances in Mathematics, Computations, and Reactor Physics by :
Download or read book Proceedings of the International Topical Meeting Advances in Mathematics, Computations, and Reactor Physics written by and published by . This book was released on 1991 with total page 498 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application by : Xingjie Peng
Download or read book Multi-Physics and Multi-Scale Modeling and Simulation Methods for Nuclear Reactor Application written by Xingjie Peng and published by Frontiers Media SA. This book was released on 2024-02-28 with total page 105 pages. Available in PDF, EPUB and Kindle. Book excerpt: A nuclear reactor operates in an environment where complex multi-physics and multi-scale phenomena exist, and it requires consideration of coupling among neutronics, thermal hydraulics, fuel performance, chemical dynamics, and coupling between the reactor core and first circuit. Safe, reliable, and economical operation can be achieved by leveraging high-fidelity numerical simulation, and proper considerations for coupling among different physics and required to provide powerful numerical simulation tools. In the past simplistic models for some of the physics phenomena are used, with the recent development of advanced numerical methods, software design, and high-performance computing power, the appeal of multi-physics and multi-scale modeling and simulation has been broadened.
Book Synopsis The History of Multiphase Science and Computational Fluid Dynamics by : Robert W. Lyczkowski
Download or read book The History of Multiphase Science and Computational Fluid Dynamics written by Robert W. Lyczkowski and published by Springer. This book was released on 2017-10-10 with total page 329 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book tells the story of how the science of computational multiphase flow began in an effort to better analyze hypothetical light water power reactor accidents, including the “loss of coolant” accident. Written in the style of a memoir by an author with 40 years’ engineering research experience in computer modeling of fluidized beds and slurries, multiphase computational fluid dynamics, and multiphase flow, most recently at Argonne National Laboratory, the book traces how this new science developed during this time into RELAP5 and other computer programs to encompass realistic descriptions of phenomena ranging from fluidized beds for energy and chemicals production, slurry transport, pyroclastic flow from volcanoes, hemodynamics of blood-borne cells, and flow of granular particulates. Such descriptions are not possible using the classical single-phase Navier-Stokes equations. Whereas many books on computational techniques and computational fluid dynamics have appeared, they do not trace the historical development of the science in any detail, and none touch on the beginnings of multiphase science. A robust, process-rich account of technologic evolution, the book is ideal for students and practitioners of mechanical, chemical, nuclear engineering, and the history of science and technology.
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1977 with total page 696 pages. Available in PDF, EPUB and Kindle. Book excerpt:
