CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors
Date
2019Author
Rousseau, Pieter G.
Du Toit, Charl G.
Van Antwerpen, Herman J.
Metadata
Show full item recordAbstract
An overview is provided of the role of the various levels of CFD in the different stages of the design, analysis and evaluation of very-high-temperature reactor (VHTR) systems and molten salt reactor (MSR) systems. The biggest challenge in this regard is to satisfy all the phenomenological, physical and time scales in a single model of the complete reactor unit. This is currently not practically feasible but rather addressed by employing models at various levels of abstraction and detail. Simulation models that encompass a large geometrical and temporal scope, such as 1D plant-wide system models, typically use reduced-order models to represent underlying phenomena. For gas-cooled pebble bed reactors a significant amount of work has been done to characterize the flow and heat transfer characteristics within the bed. For prismatic block gas-cooled reactors model development is also well advanced. Gas-cooled reactor systems in general have also been analysed exhaustively at the larger system level. In the case of liquid fuel MSRs the focus has been on multiphysics approaches wherein the neutronics are coupled with the thermal-hydraulics in order to account for the neutron precursor drift due to the velocity field. The CFD work on solid fuel MSRs employed either a porous media approach, or if the discrete element approach was employed, only focused on a very small representative unit cell geometry
URI
http://hdl.handle.net/10394/34488https://www.sciencedirect.com/science/article/pii/B9780081023372000109
https://doi.org/10.1016/B978-0-08-102337-2.00010-9
Collections
- Faculty of Engineering [1129]
Related items
Showing items related by title, author, creator and subject.
-
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 ... -
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) -
1D and 3D numerical simulation of the reactor cavity cooling system of a very high temperture reactor
Du Toit, Charl G. Jat; Rousseau, Pieter G.; Jun, Jisu S.; Noh, Jae-man (IHTC, 2014)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 RCCS can be a buoyancy ...