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Book Heat Transfer and Fluid Flow Aspects of Fuel coolant Interactions

Download or read book Heat Transfer and Fluid Flow Aspects of Fuel coolant Interactions written by M. L. Corradini and published by . This book was released on 1978 with total page 1056 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Heat Transfer and Fluid Flow Aspects of Fuel  coolant Interactions   LMFBR

Download or read book Heat Transfer and Fluid Flow Aspects of Fuel coolant Interactions LMFBR written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A major portion of the safety analysis effort for the LMFBR is involved in assessing the consequences of a Hypothetical Core Disruptive Accident (HCDA). The thermal interaction of the hot fuel and the sodium coolant during the HCDA is investigated in two areas. A postulated loss of flow transient may produce a two-phase fuel at high pressures. The thermal interaction phenomena between fuel and coolant as the fuel is ejected into the upper plenum are investigated. A postulated transient overpower accident may produce molten fuel being released into sodium coolant in the core region. An energetic coolant vapor explosion for these reactor materials does not seem likely. However, experiments using other materials (e.g., Freon/water, tin/water) have demonstrated the possibility of this phenomenon.

Book Heat transfer and fluid flow aspects of fuel cooland interactions

Download or read book Heat transfer and fluid flow aspects of fuel cooland interactions written by Michael Louis Corradini and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fuel coolant Interactions

Download or read book Fuel coolant Interactions written by M. L. Corradini and published by . This book was released on 1981 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Comparison of Predicted Nozzle Coolant Side Heat Transfer and Fluid Flow with Experimental Values from Phoebus 2A Nuclear Tests

Download or read book Comparison of Predicted Nozzle Coolant Side Heat Transfer and Fluid Flow with Experimental Values from Phoebus 2A Nuclear Tests written by Maynard F. Taylor and published by . This book was released on 1969 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Heat Transfer   Fluid Flow Digest

Download or read book Heat Transfer Fluid Flow Digest written by and published by . This book was released on 1984 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book One dimensional Transient Fluid Model for Fuel coolant Interaction Analysis

Download or read book One dimensional Transient Fluid Model for Fuel coolant Interaction Analysis written by Cho-Chone C. Chu and published by . This book was released on 1986 with total page 618 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1986 with total page 520 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1979 with total page 1074 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fuel coolant interaction in lmfbr accident analysis

Download or read book Fuel coolant interaction in lmfbr accident analysis written by A. B. Albert Barnett Reynolds and published by . This book was released on 1973 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Mechanistic Modeling of the Thermal hydraulics of Molten fuel coolant Interaction for Savannah River Site Reactors

Download or read book Mechanistic Modeling of the Thermal hydraulics of Molten fuel coolant Interaction for Savannah River Site Reactors written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A multidimensional computational-fluid dynamics (CFD) analysis has been performed of thermal-hydraulic phenomena in SRS-type reactors during hypothetical accidents caused by a partial channel blockage in the reactor core. Two specific issues have been investigated: (a) the simulation of combined flow and heat transfer in partially blocked narrow channels, and (b) parametric studies of dispersed fuel transport in high-velocity coolant flows. In the first part of the report, the issue of averaging multi-dimensional flow equations from three-dimensional (3-D) to two-dimensional (2-D) has been investigated. It has been shown that whereas good agreement can be obtained by using appropriate averaging concepts, the effect of turbulence needs special attention when simplified models are used. In the second part of this work, transport has been investigated of dispersed fuel droplets/particles carried by a high-velocity coolant from the core to the lower plenum below the core and to other components of the reactor coolant system. Parametric studies have been performed to simulate the distribution of fuel particles. It has been observed that a substantial reduction in the particle concentration occurs very close to the walls, caused only by generic hydrodynamic phenomena typical to dispersed particle flows. Such a distribution may have a significant effect on reducing particle deposition at the walls, and result in a larger amount of fuel particles flowing to other sections of the reactor system.

Book Multiphase Flow Dynamics 5

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 Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 934 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Mechanism of Liquid  liquid Contact and Heat Transfer Related to Fuel  Coolant Interactions

Download or read book Mechanism of Liquid liquid Contact and Heat Transfer Related to Fuel Coolant Interactions written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: BS>From second specialist meeting on sodium fuel interaction in fast reactors; Ispra-- Varese, Italy (21 Nov 1973). The requirements for explosive boiling (vapor explosion) are discussed with special emphasis on the UO2-Na system. Considerations include requirements for direct liquid-liquid contact and associated heat transfer characteristics. Fragmentation and explosive boiling are treated as separate phenomena. (auth).

Book Dynamic Aspects of Explosion Phenomena

Download or read book Dynamic Aspects of Explosion Phenomena written by A. L. Kuhl and published by AIAA. This book was released on 1993 with total page 602 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Applied mechanics reviews

Download or read book Applied mechanics reviews written by and published by . This book was released on 1948 with total page 400 pages. Available in PDF, EPUB and Kindle. Book excerpt: