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Development Of A Coupled Neutronics Thermal Hydraulics Fuel Thermo Mechanics Multiphysics Tool For Best Estimate Pwr Core Simulations
Download Development Of A Coupled Neutronics Thermal Hydraulics Fuel Thermo Mechanics Multiphysics Tool For Best Estimate Pwr Core Simulations full books in PDF, epub, and Kindle. Read online Development Of A Coupled Neutronics Thermal Hydraulics Fuel Thermo Mechanics Multiphysics Tool For Best Estimate Pwr Core Simulations ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Nuclear Materials for Fission Reactors by : Hj Matzke
Download or read book Nuclear Materials for Fission Reactors written by Hj Matzke and published by North Holland. This book was released on 1992 with total page 352 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non-oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO2, at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called rim effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information.
Book Synopsis Molten Salt Reactors and Thorium Energy by : Thomas James Dolan
Download or read book Molten Salt Reactors and Thorium Energy written by Thomas James Dolan and published by Elsevier. This book was released on 2024-01-25 with total page 1068 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. - A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts - Covers MSR applications, technical issues, reactor types and reactor designs - Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published - Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Book Synopsis The Design and Analysis of Computer Experiments by : Thomas J. Santner
Download or read book The Design and Analysis of Computer Experiments written by Thomas J. Santner and published by Springer. This book was released on 2019-01-08 with total page 446 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes methods for designing and analyzing experiments that are conducted using a computer code, a computer experiment, and, when possible, a physical experiment. Computer experiments continue to increase in popularity as surrogates for and adjuncts to physical experiments. Since the publication of the first edition, there have been many methodological advances and software developments to implement these new methodologies. The computer experiments literature has emphasized the construction of algorithms for various data analysis tasks (design construction, prediction, sensitivity analysis, calibration among others), and the development of web-based repositories of designs for immediate application. While it is written at a level that is accessible to readers with Masters-level training in Statistics, the book is written in sufficient detail to be useful for practitioners and researchers. New to this revised and expanded edition: • An expanded presentation of basic material on computer experiments and Gaussian processes with additional simulations and examples • A new comparison of plug-in prediction methodologies for real-valued simulator output • An enlarged discussion of space-filling designs including Latin Hypercube designs (LHDs), near-orthogonal designs, and nonrectangular regions • A chapter length description of process-based designs for optimization, to improve good overall fit, quantile estimation, and Pareto optimization • A new chapter describing graphical and numerical sensitivity analysis tools • Substantial new material on calibration-based prediction and inference for calibration parameters • Lists of software that can be used to fit models discussed in the book to aid practitioners
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201396105 Total Pages :169 pages Book Rating :4.3/5 (961 download)
Book Synopsis Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series by : International Atomic Energy Agency
Download or read book Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2013-07-01 with total page 169 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication is based on the experience of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments. Presented in this publication are the benchmark analyses of the natural circulation test performed before the definite shutdown of the reactor. The experimental data gathered during these tests represent a unique resource to carry out validation analyses and code-to-code comparisons. The benchmark analyses allowed participants to investigate and verify several system and safety codes currently used in the analyses of liquid metal thermal hydraulics phenomena in sodium fast reactors."--Publisher's description.
Book Synopsis Nuclear Power Plant Design and Analysis Codes by : Jun Wang
Download or read book Nuclear Power Plant Design and Analysis Codes written by Jun Wang and published by Woodhead Publishing. This book was released on 2020-11-10 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. - Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors - Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes - Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Book Synopsis Heat Pipe Science And Technology by : Amir Faghri
Download or read book Heat Pipe Science And Technology written by Amir Faghri and published by Global Digital Press. This book was released on 1995-03 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents basic and advanced techniques in the analytical and numerical modeling of various heat pipe systems under a variety of operating conditions and limitations. It describes the variety of complex and coupled processes of heat and mass transfer in heat pipes. The book consists of fourteen chapters, two appendices, and over 400 illustrations, along with numerous references and a wide variety of technical data on heat pipes.
Book Synopsis Proceedings of International Conference on Thermofluids by : Shripad Revankar
Download or read book Proceedings of International Conference on Thermofluids written by Shripad Revankar and published by Springer Nature. This book was released on 2020-11-21 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book presents selected and peer-reviewed proceedings of the International Conference on Thermofluids (KIIT Thermo 2020). It focuses on the latest studies and findings in the areas of fluid dynamics, heat transfer, thermodynamics, and combustion. Some of the topics covered in the book include electronic cooling, HVAC system analysis, inverse heat transfer, combustion, nano-fluids, multiphase flow, high-speed flow, and shock waves. The book includes both experimental and numerical studies along with a few review chapters from experienced researchers, and is expected to lead to new research in this important area. This book is of interest to students, researchers as well as practitioners working in the areas of fluid dynamics, thermodynamics, and combustion.
Book Synopsis Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions by : International Atomic Energy Agency
Download or read book Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions written by International Atomic Energy Agency and published by . This book was released on 2020-07-30 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.
Book Synopsis Thermal-Hydraulics of Water Cooled Nuclear Reactors by : Francesco D'Auria
Download or read book Thermal-Hydraulics of Water Cooled Nuclear Reactors written by Francesco D'Auria and published by Woodhead Publishing. This book was released on 2017-05-18 with total page 1200 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Progress on Pellet-Cladding Interaction and Stress Corrosion Cracking by : International Atomic Energy Agency
Download or read book Progress on Pellet-Cladding Interaction and Stress Corrosion Cracking written by International Atomic Energy Agency and published by . This book was released on 2021-08-15 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt: Flexible operation and related power changes can have a direct impact on fuel integrity through pellet-cladding interaction/stress corrosion cracking (PCI/SCC) phenomena, which could lead to fuel failures in certain conditions.
Book Synopsis Fluid Fuel Reactors by : James A. Lane
Download or read book Fluid Fuel Reactors written by James A. Lane and published by . This book was released on 1958 with total page 1016 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thorium—Energy for the Future by : A.K. Nayak
Download or read book Thorium—Energy for the Future written by A.K. Nayak and published by Springer. This book was released on 2019-01-30 with total page 533 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book comprises selected proceedings of the ThEC15 conference. The book presents research findings on various facets of thorium energy, including exploration and mining, thermo-physical and chemical properties of fuels, reactor physics, challenges in fuel fabrication, thorium fuel cycles, thermal hydraulics and safety, material challenges, irradiation experiences, and issues and challenges for the design of advanced thorium fueled reactors. Thorium is more abundant than uranium and has the potential to provide energy to the world for centuries if used in a closed fuel cycle. As such, technologies for using thorium for power generation in nuclear reactors are being developed worldwide. Since there is a strong global thrust towards designing nuclear reactors with thorium-based fuel, this book will be of particular interest to nuclear scientists, reactor designers, regulators, academics and policymakers.
Author :NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour Publisher :OECD ISBN 13 : Total Pages :96 pages Book Rating :4.3/5 (91 download)
Book Synopsis Scientific Issues in Fuel Behaviour by : NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour
Download or read book Scientific Issues in Fuel Behaviour written by NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour and published by OECD. This book was released on 1995 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dated January 1995
Book Synopsis Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control by : International Atomic Energy Agency
Download or read book Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control written by International Atomic Energy Agency and published by . This book was released on 1999 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report provides practical guidance on the methods available for verification of the software and validation of computer based systems in nuclear power plants, and on how and when these methods can be effectively applied. It will be of particular interest to all those involved in the development, implementation, maintenance and use of software and computer based instrumentation and control systems in nuclear power plants.
Author :National Academies of Sciences Engineering and Medicine Publisher : ISBN 13 :9780309684804 Total Pages : pages Book Rating :4.6/5 (848 download)
Book Synopsis Space Nuclear Propulsion for Human Mars Exploration by : National Academies of Sciences Engineering and Medicine
Download or read book Space Nuclear Propulsion for Human Mars Exploration written by National Academies of Sciences Engineering and Medicine and published by . This book was released on 2021-11-12 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Space Nuclear Propulsion for Human Mars Exploration identifies primary technical and programmatic challenges, merits, and risks for developing and demonstrating space nuclear propulsion technologies of interest to future exploration missions. This report presents key milestones and a top-level development and demonstration roadmap for performance nuclear thermal propulsion and nuclear electric propulsion systems and identifies missions that could be enabled by successful development of each technology.
Book Synopsis Challenges for Coolants in Fast Neutron Spectrum Systems by : International Atomic Energy Agency
Download or read book Challenges for Coolants in Fast Neutron Spectrum Systems written by International Atomic Energy Agency and published by . This book was released on 2020-07-30 with total page 268 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum (i.e. fusion, fission and accelerators), compiles the latest information in the field and identifies research needs.
Book Synopsis Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants by : International Atomic Energy Agency
Download or read book Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2007 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication summarizes the results of the Technical Meeting on "Progress in development and use of coupled codes for accident analysis". The significantly increased capacity of new computation technology has made it possible to proceed the code coupling not only between neutronics and thermal hydraulics but also between thermal hydraulics and one or more other disciplines. This publication contains a review of state-of-the-art technologies in code coupling and its application to the accident analysis of nuclear power plants. The presentations and the papers given at the Technical Meeting are enclosed on the attached CD.--Publisher's description.
