Thermal design optimization of passive cooling capability in a dry-storage system by adding wall undulations or semi-circular fins

Remache, Amel; Addad, Yacine; Sabeur-Bendehina, Amina; Ouadha, Ahmed

doi:10.1016/j.nucengdes.2019.03.028

Cited by 4 publications

(1 citation statement)

References 19 publications

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“…Although heat pipes on dry cask was shown to be useful for lowering the temperatures inside the cask, maximum temperatures are not the only safety limit to consider, mechanical limits could prove to be a challenge if such mechanisms were to be implemented. Other studies provide more conservative changes that could be relatively easily to implement like adding undulations or semi-circular fins that can increase the heat transfer coefficient in a concrete type canister (like the HI-STORM) three orders of magnitude (Remache et al, 2019).…”

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confidence: 99%

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Rodríguez¹

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One of the largest challenges facing the nuclear industry is with the management of nuclear spent fuel. As the available space in the nuclear spent pools is shrinking, nuclear power plants have needed a temporal solution to storage the nuclear spent fuel before a more definitive or a country centralized solution is coming. This necessity has been met by using nuclear dry casks. This technology has been used for a long time but with the increase in burnout in the fuel and in the casks lifetime due to lack of progress in constructing central storage facilities has meant that more knowledge is needed regarding the behavior of the fuel during this part of its cycle.In this sense, one of the key parameters is the Peak Cladding Temperature (PCT), which should not surpass 400 °C (USNRC, 2003). At that temperature, the hydrides dissolved in the clad can change their orientation and could cause embrittlement in the clads that could lead to rod failure. In order to ensure that this temperature limit is not surpass, simulations are needed to verify it. These simulations can be done with Finite Elements (FE) codes such as Ansys Mechanical and with sub-channel codes such as COBRA SFS, but the most common way to simulate the dry cask thermal behavior is through Computational Fluid Dynamics (CFD) codes like Ansys Fluent, STAR-CCM+, CFX or OpenFoam, among others.V

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confidence: 99%

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Rodríguez¹

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Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations

Wang

Lin

Chang

et al. 2021

Annals of Nuclear Energy

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Heat removal and hybrid ventilation characteristics of a vertical dry storage cask for spent nuclear fuel

Wang

Yen

Chang

et al. 2021

Nuclear Engineering and Design

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Thermal design optimization of passive cooling capability in a dry-storage system by adding wall undulations or semi-circular fins

Cited by 4 publications

References 19 publications

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations

Heat removal and hybrid ventilation characteristics of a vertical dry storage cask for spent nuclear fuel

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