2015
DOI: 10.1016/j.nucengdes.2015.01.001
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Prediction of Missouri S&T Reactor's natural convection with porous media approximation

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Cited by 11 publications
(3 citation statements)
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References 6 publications
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“…The authors of work [5] applied the porous medium model to simulate the core of a nuclear reactor, supplementing it with a heat transfer model. Papers [6][7][8] presented the results of using porous medium models to calculate the thermal hydraulics of nuclear power plant equipment. In each of these studies, the models were used to reduce the calculation time while maintaining a sufficient level of modeling accuracy.…”
Section: Heat Exchanger With Sbrcmentioning
confidence: 99%
“…The authors of work [5] applied the porous medium model to simulate the core of a nuclear reactor, supplementing it with a heat transfer model. Papers [6][7][8] presented the results of using porous medium models to calculate the thermal hydraulics of nuclear power plant equipment. In each of these studies, the models were used to reduce the calculation time while maintaining a sufficient level of modeling accuracy.…”
Section: Heat Exchanger With Sbrcmentioning
confidence: 99%
“…In this work, the CFD model utilized a user-defined equation of state model by specifying density as a function of temperature. This approach is considered to be less restrictive in terms of temperature gradient requirements and is able to capture simulated convection closer to actual conditions [19]. In order to obtain such a motion we have set all properties as a function of temperature.…”
Section: Model Assumptions and Boundarymentioning
confidence: 99%
“…The porous media model adds a source term into the momentum equation to simulate the solid resistance to the fluid flow in the calculation region [13]. The porous media model has been successfully used to simulate several types of reactors to investigate various practical problems, such as the thermal-hydraulic analysis of CARR [14], the modeling of the Missouri S&T Reactor's natural convection [15], the simulations of the fluid flow and heat transfer in the Advanced CANDU Reactor [16], and the CFD analyses of the MYRRHA primary cooling system [17].…”
Section: Introductionmentioning
confidence: 99%