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Fast Reactor Steam Generator Sodium Water Reaction Accident

Posted on:2006-02-25Degree:MasterType:Thesis
Country:ChinaCandidate:F J WengFull Text:PDF
GTID:2192360155476350Subject:Nuclear science and engineering
Abstract/Summary:PDF Full Text Request
This paper presents the numerical models of pressure source and pressure-wave propagation due to sodium-water reaction. A special code is programmed to analyze pressure source and pressure-wave propagation in the secondary coolant loop, and the code is testified with reasonableness and comparison. The results demonstrate that the numerical models are valid and reasonable.In this paper, two numerical models, a theory model and an experience model for pressure source, are provided that the numerical models of pressure source contain a theory model and an experience model. It is assumed that sodium-water reaction happened instantaneously and spherical-to-column bubble grown in the theory model of pressure source. To provide means for examining the sensitivity of the instantaneous double-ended-guillotine assumption, the examination model includes a time-dependent rupture model. Based on one-dimensional Method of Characteristics (MOC), the model of pressure-wave propagation covers some inner and outer boundary conditions.By the analysis of CEFR sodium-water reaction accident, we can draw a conclusion: 1.The pressure maximum value reach 6.7 MPa ; 2.The elasticity deformation reduces the pressure value; 3. The friction between sodium and pipe wall can be neglected.
Keywords/Search Tags:Fast Reactor, sodium-water reaction, Pressure Source, Pressure -Wave, MOC
PDF Full Text Request
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