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Numerical simulation of break flows occurring in the reactor cavity cooling system of a very high temperature reactor using a system CFD approach

Du Toit, C.G.; Rousseau, P.G.; Jun, J.S.; Kim, M.-H. (ANS (American Nuclear Society), 2016)

To avoid accidents due to human error or the failure of components, the reactor cavity cooling system (RCCS) of a high temperature reactor must be able to operate naturally or passively safe. The system under consideration ...

Comparison between Flownex and CORONA thermal-hydraulic models for a single HTR prismatic fuel assembly

Khoza, S.N.; Du Toit, C.G.; Rousseau, P.G.; Lee, S.N. (ANS (American Nuclear Society), 2016)

The flow and heat transfer in a packed bed high temperature gas-cooled reactor

Du Toit, C.G.; Rousseau, P.G. (ASME, 2010)

Engineers are faced with two major challenges when carrying out the thermal-fluid design of a complex system consisting of many interacting components such as the PBMR power plant. The first challenge is to predict the ...

Formulation of a unit cell for a thermal-hydraulic systems model of a prismatic fuel block of a high temperature gas-cooled reactor

Khoza, S.N.; Du Toit, C.G.; Rousseau, P.G. (SACAM, 2016)

A system CFD simulation of the effect of a pressure pulse on the performance of a reactor cavity cooling system of a very high temperature reactor

Du Toit, C.G.; Rousseau, P.G.; Jun, J.S.; Kim, M.W. (SACAM, 2016)

The extraction of the temperature gradient from measured temperature profiles with uncertainty propagation, as applied to the high temperature test unit

Van Antwerpen, H.J.; Rousseau, P.G.; Du Toit, C.G. (SAAM, 2010)

This paper highlights the usefulness of applying analytical methods for uncertainty analysis to a least-squares polynomial fit. It also presents an equation to calculate the confidence interval in the slope of a regression ...