Download or read book Computational Methods for Thermal and Mechanical Analysis of Nuclear Reactor Fuel Rod Transients written by Jerold Steven Marks and published by . This book was released on 1980 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Analysis of the Transient Conduction of Heat in Long Solid Cylindrical Fuel Elements for Nuclear Reactors written by Frank Eugene Tippets and published by . This book was released on 1956 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transient Three dimensional Thermal hydraulic Analysis of Nuclear Reactor Fuel Rod Arrays written by and published by . This book was released on 1975 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A mathematical model and a numerical solution scheme for thermal- hydraulic analysis of fuel rod arrays are given. The model alleviates the two major deficiencies associated with existing rod array analysis models, that of a correct transverse momentum equation and the capability of handling reversing and circulatory flows. Possible applications of the model include steady state and transient subchannel calculations as well as analysis of flows in heat exchangers, other engineering equipment, and porous media. (auth).
Download or read book Thermal Hydraulic Analysis of Nuclear Reactors written by Bahman Zohuri and published by Springer. This book was released on 2017-05-23 with total page 845 pages. Available in PDF, EPUB and Kindle. Book excerpt: This revised 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. The book begins 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. 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. There have been significant new findings for intercooled systems since the previous edition published and they will be included in this volume. New technology plans for using a Nuclear Air-Brayton as a storage system for a low carbon grid are presented along with updated component sizes and performance criteria for Small Modular Reactors. 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.
Download or read book SCORE EVET written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-dimensional steady state solution scheme to initialize the flow field, (b) steady state and transient fuel rod conduction models, and (c) comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Improved Multidimensional Numerical Methods for the Steady State and Transient Thermal hydraulic Analysis of Fuel Pin Bundles and Nuclear Reactor Cores written by Robert Edward Masterson and published by . This book was released on 1977 with total page 239 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Multiphase Flow Dynamics 4 written by Nikolay Ivanov Kolev and published by Springer Science & Business Media. This book was released on 2009-06-12 with total page 761 pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear thermal hydraulic is the science providing knowledge about the physical processes occurring during the transferring the fission heat released in structural materials due to nuclear reactions into its environment. Along its way to the environment the thermal energy is organized to provide useful mechanical work or useful heat or both. Chapter 1 contains introductory information about the heat release in the re- tor core, the thermal power and thermal power density in the fuel, structures and moderator, the influence of the thermal power density on the coolant temperature, the spatial distribution of the thermal power density. Finally some measures are introduced for equalizing of the spatial distribution of the thermal power density. Chapter 2 gives the methods for describing of the steady and of the transient temperature fields in the fuel elements. Some information is provided regarding influence of the cladding oxidation, hydrogen diffusion and of the corrosion pr- uct deposition on the temperature fields. Didactically the nuclear thermal hydraulic needs introductions at different level of complexity by introducing step by step the new features after the previous are clearly presented. The followed two Chapters serve this purpose. Chapter 3 describes mathematically the “simple” steady boiling flow in a pipe. The steady mass-, momentum- and energy conservation equations are solved at different level of complexity by removing one after the other simplifying assu- tions. First the idea of mechanical and thermodynamic equilibrium is introduced.
Download or read book GAPCON 3 written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: GAPCON-3 provides an integrated thermal and mechanical analysis of a reactor fuel pin in terms of its path-dependent power history. It is designed to handle the axial and radial variations in power, temperature, and fuel cladding mechanical interaction, normally encountered in LWR fuel. It provides detailed information regarding temperatures, stresses, and strains depending upon the mesh size selected and the needs of the user. The code uses a finite element formulation for the mechanical analysis and includes the effects of creep, plasticity, and anisotropy. The steady state thermal calculations are based upon the method of weighted residuals (MWR) and use a finite difference formulation for treating the transient thermal dependence. The fuel behavior models incorporate relocation, swelling, and densification as well as power history-dependent local fission gas release. The code is structured to operate efficiently and to allow its use in both parametric as well as detailed analysis applications. A typical problem on a CDC-6600 computer will require 8 to 10 seconds per time step for solution.
Download or read book Unsteady Thermal Analysis of Gas cooled Fast Reactor written by Issam Adnan Lakkis and published by . This book was released on 1993 with total page 484 pages. Available in PDF, EPUB and Kindle. Book excerpt: This thesis presents numerical analysis of transient heat transfer in an equivalent coolant - fuel rod cell of a typical gas cooled, fast nuclear reactor core. The transient performance is assumed to follow a complete sudden loss of coolant starting from steady state operation Steady state conditions are obtained from solving a conduction problem in the fuel rod and a parabolic turbulent convection problem in the coolant section. The coupling between the two problems is accomplished by ensuring continuity of the thermal conditions at the interface between the fuel rod and the coolant. To model turbulence, the mixing length theory is used various fuel rod configurations have been tested for optimal transient performance. Actually, the loss of coolant accident occurs gradually at an exponential rate Moreover, a time delay before shutting down the reactor by full insertion of control rods usually exists. It is required to minimize maximum steady state cladding temperature so that the time required to reach its limiting value during transient state is maximum. This will prevent the escape of radioactive gases that endanger the environment and the public. However, the case considered here is a limiting case representing what could actually happen in the worst probable accident. So, the results in this thesis are very indicative regarding selection of the fuel rod configuration for better transient performance in case of accidents in which complete loss of coolant occurs instantaneously. Selection of the fuel rod configuration was done by one or a combination of the following procedures: adding high thermal property materials (dilutcnts) such as S.S., UO;, etc., vary ing the ratio (ft) of the volume of the added material to the volume of the fuel in the fuel rod, varying the location of the added material, and allowing a part of the coolant to flow through a central channel in the fuel rod so that it is cooled from both the inner and the outer sides It should he noled that the volumetric ratio R is of great importance since it affects the nuclear performance of the core initially, when R = 0, i.e., no dilutent is added, the nuclear performance of the core is called "Fast." However, as R increases, the core starts to get nearer to the 'Thermal" performance, resulting in a major change in the design of the reactor .So, to keep the reactor fast, R shouldn't be increased above the threshold value Rfh. The heat source present in the fuel is obtained from analytical solution of the neutron flux diffusion equation using one group theory. The unavailability of data made it impossible to use the multigroup theory to solve for the neutron flux and the heat source distribution.
Download or read book ERDA Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976 with total page 716 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Super Light Water Reactors and Super Fast Reactors written by Yoshiaki Oka and published by Springer Science & Business Media. This book was released on 2010-07-01 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
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 1976-05 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutronics Methods for Transient and Safety Analysis of Fast Reactors written by Marchetti, Marco and published by KIT Scientific Publishing. This book was released on 2017-03-02 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 2020-11-27 with total page 610 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.
Download or read book Thermal and Reactor Analysis of Nuclear Rocket Transients written by Robert R. Mills and published by . This book was released on 1973 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 1977 with total page 982 pages. Available in PDF, EPUB and Kindle. Book excerpt:
