2009
DOI: 10.1007/s00371-008-0309-x
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Visual simulation of thermal fluid dynamics in a pressurized water reactor

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Cited by 7 publications
(3 citation statements)
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“…We present a simulation and visualization system for a critical application-the analysis of the thermal fluid dynamics inside a pressurized water reactor (PWR) of a nuclear power plant when cold water is injected into the reactor vessel. We have worked closely with PWR scientific engineers and have developed a visual simulation system [2] that employs a hybrid thermal lattice Boltzmann method (HTLBM) [7] for modeling of the thermal fluid dynamics. In particular, the simulation demonstrates the formation of cold-water plumes in the reactor vessel.…”
Section: Application: Thermal Fluid Dynamics In a Pressurized Water Rmentioning
confidence: 99%
“…We present a simulation and visualization system for a critical application-the analysis of the thermal fluid dynamics inside a pressurized water reactor (PWR) of a nuclear power plant when cold water is injected into the reactor vessel. We have worked closely with PWR scientific engineers and have developed a visual simulation system [2] that employs a hybrid thermal lattice Boltzmann method (HTLBM) [7] for modeling of the thermal fluid dynamics. In particular, the simulation demonstrates the formation of cold-water plumes in the reactor vessel.…”
Section: Application: Thermal Fluid Dynamics In a Pressurized Water Rmentioning
confidence: 99%
“…Possible fractures in the reactor after a Small Break-Loss Of Coolant Accident (SB-LOCA), by a high-temperature gradient following the emergency cold injection by a high-pressure injection system [42,43].…”
mentioning
confidence: 99%
“…More sophisticated turbulence models, such as VLES or LES-WALE [44,52,54,55,58], are also used, leading to better results than LES, and that of the use of the LBM (only without taking into account turbulence). The inclusion of thermal field models is relevant [42,43,53,55,56] to upgrade the classical isothermal LBM to a numerical method capable of simulating the heat transfer mechanisms present in the reactor (in particular, the convective heat transfer). The most commonly used is based on the secondary distribution approach.…”
mentioning
confidence: 99%