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A Nodal Method For Multigroup Multidimensional Nuclear Reactor Dynamics With Thermal Hydraulics Feedback
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Book Synopsis A Nodal Method for Multigroup, Multidimensional Nuclear Reactor Dynamics with Thermal-hydraulics Feedback by : Thuy Trong Le
Download or read book A Nodal Method for Multigroup, Multidimensional Nuclear Reactor Dynamics with Thermal-hydraulics Feedback written by Thuy Trong Le and published by . This book was released on 1990 with total page 632 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 A Quasi-static Polynomial Nodal Method for Nuclear Reactor Analysis by :
Download or read book A Quasi-static Polynomial Nodal Method for Nuclear Reactor Analysis written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Modern nodal methods are currently available which can accurately and efficiently solve the static and transient neutron diffusion equations. Most of the methods, however, are limited to two energy groups for practical application. The objective of this research is the development of a static and transient, multidimensional nodal method which allows more than two energy groups and uses a non-linear iterative method for efficient solution of the nodal equations. For both the static and transient methods, finite-difference equations which are corrected by the use of discontinuity factors are derived. The discontinuity factors are computed from a polynomial nodal method using a non-linear iteration technique. The polynomial nodal method is based upon a quartic approximation and utilizes a quadratic transverse-leakage approximation. The solution of the time-dependent equations is performed by the use of a quasi-static method in which the node-averaged fluxes are factored into shape and amplitude functions. The application of the quasi-static polynomial method to several benchmark problems demonstrates that the accuracy is consistent with that of other nodal methods. The use of the quasi-static method is shown to substantially reduce the computation time over the traditional fully-implicit time-integration method. Problems involving thermal-hydraulic feedback are accurately, and efficiently, solved by performing several reactivity/thermal-hydraulic updates per shape calculation.
Book Synopsis Mathematical Nodal Method for Energy-space-time Nuclear Reactor Dynamics by : Thuy Trong Le
Download or read book Mathematical Nodal Method for Energy-space-time Nuclear Reactor Dynamics written by Thuy Trong Le and published by . This book was released on 1987 with total page 254 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multiphase Flow Dynamics 5 by : Nikolay Ivanov Kolev
Download or read book Multiphase Flow Dynamics 5 written by Nikolay Ivanov Kolev and published by Springer Science & Business Media. This book was released on 2011-10-18 with total page 839 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demonstrate the success of the different ideas and models. After an introduction of the design of the reactor pressure vessels for pressurized and boiling water reactors the accuracy of the modern methods is demonstrated using large number of experimental data sets for steady and transient flows in heated bundles. Starting with single pipe boiling going through boiling in the rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then a powerful method for nonlinear stability analysis of flow boiling and condensation is introduced. Models are presented and their accuracies are investigated for describing critical multiphase flow at different level of complexity. Basics of designing of steam generators, moisture separators and emergency condensers are presented. Methods for analyzing a complex pipe network flows with components like pumps, valves etc. are also presented. Methods for analysis of important aspects of the severe accidents like melt-water interactions, external cooling and cooling of layers of molten nuclear reactor material are presented. Valuable sets of thermo-physical and transport properties for severe accident analysis are presented for the following materials: uranium dioxide, zirconium dioxide, stainless steel, zirconium, aluminum, aluminum oxide, silicon dioxide, iron oxide, molybdenum, boron oxide, reactor corium, sodium, lead, bismuth, and lead-bismuth eutectic alloy. The emphasis is on the complete and consistent thermo dynamical sets of analytical approximations appropriate for computational analysis. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics. This present second edition includes various updates, extensions, improvements and corrections. This present second edition includes various updates, extensions, improvements and corrections.
Book Synopsis Dissertation Abstracts International by :
Download or read book Dissertation Abstracts International written by and published by . This book was released on 1991 with total page 802 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book FX2-TH written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: FX2-TH is a two-dimensional, time-dependent nuclear reactor kinetics program with thermal and hydraulic feedback. The neutronics model used is multigroup neutron diffusion theory. The following geometry options are available: x, r, x-y, r-z, theta-r, and triangular. FX2-TH contains two basic thermal and hydraulic models: a simple adiabatic fuel temperature calculation, and a more detailed model consisting of an explicit representation of a fuel pin, gap, clad, and coolant. FX2-TH allows feedback effects from both fuel temperature (Doppler) and coolant temperature (density) changes. FX2-TH will calculate a consistent set of steady state conditions by iterating between the neutronics and thermal-hydraulics until convergence is reached. The time-dependent calculation is performed by the use of the improved quasistatic method. A disk editing capability is available. FX2-TH is operational on IBM system 360 or 370 computers and on the CDC 7600.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1987 with total page 1316 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis American Doctoral Dissertations by :
Download or read book American Doctoral Dissertations written by and published by . This book was released on 1990 with total page 768 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 1320 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Energy Research and Development Administration. Technical Information Center Publisher : ISBN 13 : Total Pages :588 pages Book Rating :4.3/5 (129 download)
Book Synopsis ERDA Energy Research Abstracts by : United States. Energy Research and Development Administration. Technical Information Center
Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration. Technical Information Center and published by . This book was released on 1976 with total page 588 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Transactions of the American Nuclear Society by : American Nuclear Society
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1999 with total page 788 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the Topical Meeting on Computational Methods in Nuclear Engineering by :
Download or read book Proceedings of the Topical Meeting on Computational Methods in Nuclear Engineering written by and published by . This book was released on 1979 with total page 346 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :University of Illinois (Urbana-Champaign campus). Engineering Experiment Station Publisher : ISBN 13 : Total Pages :416 pages Book Rating :4.:/5 (31 download)
Book Synopsis The Summary of Engineering Research by : University of Illinois (Urbana-Champaign campus). Engineering Experiment Station
Download or read book The Summary of Engineering Research written by University of Illinois (Urbana-Champaign campus). Engineering Experiment Station and published by . This book was released on 1995 with total page 416 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Dissertation Index by :
Download or read book Comprehensive Dissertation Index written by and published by . This book was released on 1984 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1985 with total page 966 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
