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Multi Scale Multi Physics Modeling Of Metallic Fuel And Thermal Hydraulics Of Sodium Fast Reactors In A Subchannel Approach
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Book Synopsis Multi-scale Multi-Physics Modeling of Metallic Fuel and Thermal Hydraulics of Sodium Fast Reactors in a Subchannel Approach by : Ahmed Mohamed Nabil Hassanein Aly
Download or read book Multi-scale Multi-Physics Modeling of Metallic Fuel and Thermal Hydraulics of Sodium Fast Reactors in a Subchannel Approach written by Ahmed Mohamed Nabil Hassanein Aly and published by . This book was released on 2022 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors by : Ferry Roelofs
Download or read book Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors written by Ferry Roelofs and published by Woodhead Publishing. This book was released on 2018-12-07 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge.
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 Dynamic Simulation of Sodium Cooled Fast Reactors by : G Vaidyanathan
Download or read book Dynamic Simulation of Sodium Cooled Fast Reactors written by G Vaidyanathan and published by CRC Press. This book was released on 2022-11-18 with total page 273 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides the basis of simulating a nuclear plant, in understanding the knowledge of how such simulations help in assuring the safety of the plants, thereby protecting the public from accidents. It provides the reader with an in-depth knowledge about modeling the thermal and flow processes in a fast reactor and gives an idea about the different numerical solution methods. The text highlights the application of the simulation to typical sodium-cooled fast reactor. The book • Discusses mathematical modeling of the heat transfer process in a fast reactor cooled by sodium. • Compares different numerical techniques and brings out the best one for the solution of the models. • Provides a methodology of validation based on experiments. • Examines modeling and simulation aspects necessary for the safe design of a fast reactor. • Emphasizes plant dynamics aspects, which is important for relating the interaction between the components in the heat transport systems. • Discusses the application of the models to the design of a sodium-cooled fast reactor It will serve as an ideal reference text for senior undergraduate, graduate students, and academic researchers in the fields of nuclear engineering, mechanical engineering, and power cycle engineering.
Book Synopsis Integrated Fuel Performance and Thermal-hydraulic Sub-channel Models for Analysis of Sodium Fast Reactors by : Joseph William Fricano
Download or read book Integrated Fuel Performance and Thermal-hydraulic Sub-channel Models for Analysis of Sodium Fast Reactors written by Joseph William Fricano and published by . This book was released on 2012 with total page 257 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sodium Fast Reactors (SFR) show promise as an effective way to produce clean safe nuclear power while properly managing the fuel cycle. Accurate computer modeling is an important step in the design and eventual licensing of SFRs. The objective of this work was to couple a model for metal fuel performance to a sub-channel analysis code to more precisely predict critical phenomena that could lead to pin failure for steady-state and transient scenarios. The fuel code that was used is the recently developed and benchmarked FEAST-METAL code. The sub-channel analysis code that was selected is COBRA-IV-I. This code was updated with current correlations for sodium for pressure drop, mixing, and heat transfer. The new code, COBRA-IV-I-MIT was then validated with experimental data from the Oak Ridge National Laboratory (ORNL) 19-Pin Bundle, the Toshiba 37-Pin Bundle, and the Westinghouse Advanced Reactors Division (WARD) 61-Pin Bundle. Important topics that were addressed for coupling the codes include the following. The importance of azimuthal effects in the fuel pin: FEAST only evaluates the fuel in two-dimensions, assuming azimuthal symmetry; however, coupling to COBRA produces an azimuthal temperature distribution. The acceptability of assuming a two-dimensional fuel rod with an average temperature was examined. Furthermore, how the fuel pin evolves over time affects the assembly geometry. How well a two-dimensional fuel rod allows for an accurate description of the changing assembly geometry was also considered. Related to this was how the evolution of the assembly geometry affects its thermal hydraulic behavior, which determined the exact form of coupling between the codes. Ultimately one-way coupling was selected with azimuthal temperature averaging around the fuel pin. The codes were coupled using a wrapper, the COBRA And FEAST Executer (CAFE), written in the Python programming language. Data from EBR-II was used to confirm and verify CAFE. It was found that the number of axial nodes used in FEAST can have a large effect on the result. Finally FEAST was used to parametrically study three different pin designs: driver fuel, radial blanket, and tight pitch breed and bum fuel. This study provides data for pin expected life in assembly design.
Book Synopsis Thermal-hydraulic Numerical Simulation of Fuel Sub-assembly for Sodium-cooled Fast Reactor by : Aakanksha Saxena
Download or read book Thermal-hydraulic Numerical Simulation of Fuel Sub-assembly for Sodium-cooled Fast Reactor written by Aakanksha Saxena and published by . This book was released on 2014 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The thesis focuses on the numerical simulation of sodium flow in wire wrapped sub-assembly of Sodium-cooled Fast Reactor (SFR).First calculations were carried out by a time averaging approach called RANS (Reynolds- Averaged Navier-Stokes equations) using industrial code STAR-CCM+. This study gives a clear understanding of heat transfer between the fuel pin and sodium. The main variables of the macroscopic flow are in agreement with correlations used hitherto. However, to obtain a detailed description of temperature fluctuations around the spacer wire, more accurate approaches like LES (Large Eddy Simulation) and DNS (Direct Numerical Simulation) are clearly needed. For LES approach, the code TRIO_U was used and for the DNS approach, a research code was used. These approaches require a considerable long calculation time which leads to the need of representative but simplified geometry.The DNS approach enables us to study the thermal hydraulics of sodium that has very low Prandtl number inducing a very different behavior of thermal field in comparison to the hydraulic field. The LES approach is used to study the local region of sub-assembly. This study shows that spacer wire generates the local hot spots (~20°C) on the wake side of spacer wire with respect to the sodium flow at the region of contact with the fuel pin. Temperature fluctuations around the spacer wire are low (~1-2°C). Under nominal operation, the spectral analysis shows the absence of any dominant peak for temperature oscillations at low frequency (2-10Hz). The obtained spectra of temperature oscillations can be used as an input for further mechanical studies to determine its impact on the solid structures.
Book Synopsis Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors by : AYDIN KARAHAN
Download or read book Modeling of Metallic and Oxide Fuel Behavior for Sodium Fast Reactors written by AYDIN KARAHAN and published by . This book was released on 2010-03 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors by : Lelio Luzzi
Download or read book Multi-physics Approach to the Modelling and Analysis of Molten Salt Reactors written by Lelio Luzzi and published by Nova Novinka. This book was released on 2012 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Multi-Physics Modelling (MPM) is an innovative simulation technique that looks very promising for the employment in the field of nuclear engineering as an integrative analysis support in the design development of current and innovative nuclear reactors. This book presents a Multi-Physics Modelling (MPM) approach to the analysis of nuclear reactor core behaviour, developed to study the coupling between neutronics and thermo-hydrodynamics. Reference is made to the Molten Salt Reactor, one of the innovative nuclear systems under development in the framework of the Generation IV International Forum, but the same methodology can be applied to other reactor systems.
Book Synopsis A Framework for Multi-physics Modeling, Design Optimization and Uncertainty Quantification of Fast Spectrum Liquid Fuel Molten Salt Reactors by : Sandesh Bhaskar
Download or read book A Framework for Multi-physics Modeling, Design Optimization and Uncertainty Quantification of Fast Spectrum Liquid Fuel Molten Salt Reactors written by Sandesh Bhaskar and published by . This book was released on 2022 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Analysis of Liquid-metal Fast Breeder Reactors by : Yu S. Tang
Download or read book Thermal Analysis of Liquid-metal Fast Breeder Reactors written by Yu S. Tang and published by American Nuclear Society. This book was released on 1978 with total page 432 pages. Available in PDF, EPUB and Kindle. Book excerpt: This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.
Book Synopsis Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients by : J. M. Kramer
Download or read book Modeling the Behavior of Metallic Fast Reactor Fuels During Extended Transients written by J. M. Kramer and published by . This book was released on 1992 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal-hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor by : Matthew J. Memmott
Download or read book Thermal-hydraulic Analysis of Innovative Fuel Configurations for the Sodium Fast Reactor written by Matthew J. Memmott and published by . This book was released on 2009 with total page 458 pages. Available in PDF, EPUB and Kindle. Book excerpt: (Cont.) As an application of this subchannel model, duct ribs were explored as a means of reducing core outlet temperature peaking within the fuel assemblies. The performance of the annular and bottle-shaped fuel was also investigated using this subchannel model. The annular fuel configurations are best suited for low conversion ratio cores. The magnitude of the power uprate enabled by metal annular fuel in the CR = 0.25 cores is 20%, and is limited by the FCCI constraint during a hypothetical flow blockage of the inner-annular channel due to the small diameters of the inner-annular flow channel (3.6 mm). On the other hand, a complete blockage of the hottest inner-annular flow channel in the oxide fuel case results in sodium boiling, which renders the annular oxide fuel concept unacceptable for use in a SFR. The bottle-shaped fuel configurations are best suited for high conversion ratio cores. In the CR = 0.71 cores, the bottle-shaped fuel configuration reduces the overall core pressure drop in the fuel channels by up to 36.3%. The corresponding increase in core height with bottle-shaped fuel is between 15.6% and 18.3%. A full-plant RELAP5-3D model was created to evaluate the transient performance of the base and innovative fuel configurations during station blackout and UTOP transients. The transient analysis confirmed the good thermal-hydraulic performance of the annular and bottle-shaped fuel designs with respect to their respective solid fuel pin cases.
Book Synopsis Multi-scale, Multi Physics Modeling of Thermo-chemical Iron/iron Oxide Cycle for Fuel Production by : Abhishek Kumar Singh
Download or read book Multi-scale, Multi Physics Modeling of Thermo-chemical Iron/iron Oxide Cycle for Fuel Production written by Abhishek Kumar Singh and published by . This book was released on 2013 with total page 155 pages. Available in PDF, EPUB and Kindle. Book excerpt: A collision based Monte Carlo ray tracing model is developed and coupled to the lattice Boltzmann conduction model to optimize the geometry of the windowless horizontal cavity reactor. Finally, for the reactive material scale analysis, a participating medium Monte Carlo ray tracing code is created for the continuum model involving heat and mass transfer coupled with chemical kinetics to investigate the effect of various parameters (such as operating temperature, input steam flow rate, steam concentration) on hydrogen production.
Book Synopsis Improvement of High-to-low Fidelity Multi-physics Modeling for Sodium-cooled Fast Reactor Cores by : Cole Nathaniel Takasugi
Download or read book Improvement of High-to-low Fidelity Multi-physics Modeling for Sodium-cooled Fast Reactor Cores written by Cole Nathaniel Takasugi and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis FAST REACTOR FUEL ASSEMBLY THERMAL HYDRAULIC DEVELOPMENT PROGRAM by :
Download or read book FAST REACTOR FUEL ASSEMBLY THERMAL HYDRAULIC DEVELOPMENT PROGRAM written by and published by . This book was released on 1970 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reynolds-Averaged Navier-Stokes-based Thermal-hydraulic Investigation of the Sodium Cooled Fast Reactor Standard Fuel Bundle, Altered Bundles, and Spacer Grids by : Jeffrey Gordon Smith
Download or read book Reynolds-Averaged Navier-Stokes-based Thermal-hydraulic Investigation of the Sodium Cooled Fast Reactor Standard Fuel Bundle, Altered Bundles, and Spacer Grids written by Jeffrey Gordon Smith and published by . This book was released on 2010 with total page 280 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutronics and Thermal-hydraulics Coupling by : Maxime Guyot
Download or read book Neutronics and Thermal-hydraulics Coupling written by Maxime Guyot and published by . This book was released on 2014 with total page 239 pages. Available in PDF, EPUB and Kindle. Book excerpt: This project is dedicated to the analysis and the quantification of bias corresponding to the computational methodology for simulating the initiating phase of severe accidents on Sodium Fast Reactors. A deterministic approach is carried out to assess the consequences of a severe accident by adopting best estimate design evaluations. An objective of this deterministic approach is to provide guidance to mitigate severe accident developments and recriticalities through the implementation of adequate design measures. These studies are generally based on modern simulation techniques to test and verify a given design. The new approach developed in this project aims to improve the safety assessment of Sodium Fast Reactors by decreasing the bias related to the deterministic analysis of severe accident scenarios.During the initiating phase, the subassembly wrapper tubes keep their mechanical integrity. Material disruption and dispersal is primarily one-dimensional. For this reason, evaluation methodology for the initiating phase relies on a multiple-channel approach. Typically a channel represents an average pin in a subassembly or a group of similar subassemblies. Inthe multiple-channel approach, the core thermal-hydraulics model is composed of 1 or 2 D channels. The thermal-hydraulics model is coupled to a neutronics module to provide an estimate of the reactor power level.In this project, a new computational model has been developed to extend the initiating phase modeling. This new model is based on a multi-physics coupling. This model has been applied to obtain information unavailable up to now in regards to neutronics and thermal-hydraulics models and their coupling.
