Molten Fuel Coolant Interactions in Entrapment Configuration PDF Download
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Author: Ralf Büttner
Publisher:
ISBN:
Category :
Languages : en
Pages : 73
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Author: Ralf Büttner
Publisher:
ISBN:
Category :
Languages : en
Pages : 73
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Author: B. D. Turland
Publisher:
ISBN: 9789282767559
Category :
Languages : en
Pages : 132
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Author: Seungho Han
Publisher:
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Category :
Languages : en
Pages :
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Author: Patricia Pla
Publisher: LAP Lambert Academic Publishing
ISBN: 9783838311081
Category :
Languages : en
Pages : 180
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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.
Author: Niko Spitznagel
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: M. L. Corradini
Publisher:
ISBN:
Category : Explosions
Languages : en
Pages : 113
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Author: D. H. Cho
Publisher:
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Category : Heat
Languages : en
Pages : 0
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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This paper describes a simple fuel melt slumping model to replace the current parametric model in SCDAP/RELAP5. Specifically, a fuel-coolant interaction (FCI) model is developed to analyze the slumping molten fuel, molten fuel breakup, heat transfer to coolant, relocation of the molten droplets, size of a partially solidified particles that settle to the bottom of the lower plenum, and melt-plenum interaction, if any. Considering our objectives, the molten fuel jet breakup model, and fuel droplets Lagrangian model as included in a code TEXAS-V with Eulerian thermal hydraulics for water and steam from SCDAP/RELAP5 were used. The model was assessed with experimental data from MAGICO-2000 tests performed at University of California at Santa Barbara, and FARO Test L-08 performed at Joint Research Center, Ispra, Italy. The comparison was found satisfactory.
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Category :
Languages : en
Pages :
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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.
Author: Mujid Suliman Kazimi
Publisher:
ISBN:
Category :
Languages : en
Pages :
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