Title of article :
Multidimensional analysis of fission gas transport following fuel element failure in sodium fast reactor
Author/Authors :
Bolotnov، نويسنده , , Igor A. and Antal، نويسنده , , Steven P. and Jansen، نويسنده , , Kenneth E. and Podowski، نويسنده , , Michael Z.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2012
Pages :
11
From page :
136
To page :
146
Abstract :
Significant progress in several areas will have to be made to achieve the required technological and safety standards for future Gen. IV reactors, including both novel experimental methods (starting with separate-effect, then followed by integral experiments) and high performance computational models characterized by the necessary level of modeling detail and high accuracy of predictions. Furthermore, it is important that the experimental and theoretical/computational research complement each other, so that the results of measurements could be directly used for model validation purposes, whereas the results of simulations should provide input to identify modeling uncertainties and provide guidelines for prioritizing future experiments. rpose of this paper is to present the modeling concept for mechanistic computer simulations of the injection of a jet of gaseous fission products into a partially blocked SFR coolant channel following localized cladding overheat and breach. A three-dimensional model of gas/liquid-sodium interaction has been developed based on a multifield modeling framework implemented in the NPHASE-CMFD code. The boundary conditions used as input to NPHASE-CMFD have been obtained by averaging the results of direct numerical simulations (DNS) performed using the PHASTA code. The novel aspects of the results discussed in the paper include the demonstration of advantages of using a multiscale approach to model local phenomena governing gas/liquid-sodium two-phase flow inside reactor coolant channels following cladding breach, as well as the observations about areas where future experiments are needed to improve the predictive capabilities of two-phase flow models.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2012
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1592184
Link To Document :
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