Download or read book Characterisation of Molten fuel Coolant Interaction Processes MFCI written by D. Magallon and published by . This book was released on 2000 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modelling Molten Fuel Coolant Interaction written by Patricia Pla and published by LAP Lambert Academic Publishing. This book was released on 2009-08 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt: Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available water for core cooling. During SA the reactor core could, after partial/total melt down, pour into the lower plenum. The study of the interaction of melt fuel with water is the objective of MFCI (Melt Fuel Coolant Interaction). MFCI is an important issue in reactor safety . A SA can lead to energetic (steam explosion) or non-energetic (melt quenching) interactions in-vessel or ex-vessel. FARO facility at JRC-Ispra simulated MFCI experiments under real conditions. Pre-test/post-test analytical activities using COMETA code were carried out. The code was assessed based on FARO tests. Limitations and uncertainties in the application to a full plant needed to be identified and quantified. The PhD research objective was achieved expanding the knowledge in MFCI. It was complemented with application of COMETA to conditions not experimented before, developing and improving COMETA sources and verifying code consistency, analysing and unifying the COMETA simulations. An analytical study was carried out to illustrate the MFCI inside a NPP SA sequence.
Download or read book Assessment of Size Aspects in Modelling Molten Fuel Coolant Interaction written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ABSTRACT Severe accidents in light water nuclear reactors occur when reactor vessel water inventory decreases and there is no available additional water coolant to be delivered into the core. In general, during an extended severe accident sequence a period exists in which the reactor core, after a partial or total melt down, is poured into the lower plenum that can have some water present. The study of the interaction of the melt fuel with the water is the objective of MFCI (Melt Fuel Coolant Interaction) activities. MFCI is one of the most important issues awaiting resolution in water cooled reactor safety analysis. The progression of a severe accident in a water cooled reactor can lead to energetic (steam explosion) or non-energetic (melt quenching) interactions as the molten fuel relocates and eventually interacts with the coolant either in the vessel lower head (in vessel) or in the cavity (ex-vessel). The MFCI experiments at JRC Ispra site were conducted in the FARO (Furnace And Release Oven) test facility under realistic melt composition and prototypical accident conditions to provide basic information on underlying phenomena. The experimental programme was complemented by comprehensive pre-test and post-test analytical activities based on the development and application of the thermalhydraulic COMETA (COre MElt Thermalhydraulic Analysis) code. The code is developed and assessed on the basis of experimental information acquired in the FARO facility tests, and there are some limitations and uncertainties in their application to the full plant, which need to be identified and possibly quantified. In general the main objective of the PhD research was achieved expanding the general knowledge in Melt Fuel Coolant Interaction. The knowledge was complemented collaborating and complementing the application of COMETA code under conditions not experimented before, developing and improving COMETA code sources and verifying the code consistency, analysing and unifying the.
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 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.
Download or read book Molten Fuel Coolant Interactions written by B. D. Turland and published by . This book was released on 1996 with total page 132 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Transfer During Molten Fuel Coolant Interaction written by Niko Spitznagel and published by . This book was released on 2016 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Assessment of size aspects in modelling molten fuel coolant interaction written by Patricia Pla Freixa and published by . This book was released on 2003 with total page 167 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1058 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Molten Fuel coolant Interactions written by Seungho Han and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Rate limited Model of Molten Fuel coolant Interactions written by D. H. Cho and published by . This book was released on 1972 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Theoretical Studies of Some Aspects of Molten Fuel coolant Thermal Interactions written by Mujid Suliman Kazimi and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Molten Fuel Coolant Interactions in Entrapment Configuration written by Ralf Büttner and published by . This book was released on 1997 with total page 73 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modelling the transient pressurisation during a molten fuel coolant interaction written by D. F. Fletcher and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fuel coolant Interactions written by M. L. Corradini and published by . This book was released on 1981 with total page 113 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fuel Coolant Interactions Under Forced Mixing Conditions written by and published by . This book was released on 1997 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: In a postulated severe accident scenario, a fuel channel in the core of a CANDU reactor becomes blocked and the fuel melts. The molten fuel may be ejected into the surrounding moderator. This report examines the existing literature relevant to the possibility of a fuel coolant interaction under these circumstances. Four experimental studies are identified and discussed in which the initial ejection of molten fuel into coolant approximates the postulated accident scenario. Currently available codes for predicting fuel coolant interaction are also reviewed. Finally, an experimental program is proposed to supplement the existing data base and resolve the probability of a fuel coolant interaction under forced mixing conditions.
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:
