Gen-IV pool reactors: Validation of sloshing CFD modelling and behavior under large seismic events

• Sloshing in a large vertical cylinder is numerically validated. • Sloshing of a mock-up of the Gen-IV ALFRED reactor is simulated. • Effects on the mock-up of large seismic events are numerically investigated. • Impact forces on components are dominated by seismic high frequencies. • Impact forces due to sloshing are only marginal. This paper addresses one aspect of the safety of compact lead-cooled pool fast reactors. Under a seismic event, there is concern that the surface sloshing could compromise the integrity of some structures or components. We investigate this issue by means of computational modelling and simulation using the STAR-CCM + commercial software. In the first part, we simulate a partially filled vertical cylinder under harmonic forcing and quantitatively validate the modelling by comparison with experimental data of the free-surface height at different locations. Specifically, we capture with a very high precision a behavioral transition of the amplitude-frequency map near resonance. In the second part, the modelling is applied to a fast reactor mock-up in water. It is validated again by comparison with experimental data under harmonic forcing. The numerical mock-up is then subjected to four seismic events of increasing intensity. The free-surface height and the forces applied to the mock-up vessel are monitored. It is found that the forces applied to the vessel are strongly dominated by the highest frequency of the seismic acceleration. By applying a high filter cut at 1 Hz, the peak force is reduced by one order of magnitude but remains strongly related to the damped acceleration signal. Even then, sloshing forcing effects are observed but remain marginal.

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Publication Details

Journal
Nuclear Engineering and Design
Published
2025-02-20
DOI
https://doi.org/10.1016/j.nucengdes.2025.113920
Citations
1
Primary Topic
Fluid Dynamics Simulations and Interactions
Type
article
Field-Weighted Citation Impact
1.33
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article

Gen-IV pool reactors: Validation of sloshing CFD modelling and behavior under large seismic events

Manuela Profir, Vincent Moreau
1 citations
Nuclear Engineering and Design
Fluid Dynamics Simulations and Interactions
1.33
article

Gen-IV pool reactors: Validation of sloshing CFD modelling and behavior under large seismic events

Manuela Profir, Vincent Moreau
article en
1 citations

Abstract

• Sloshing in a large vertical cylinder is numerically validated. • Sloshing of a mock-up of the Gen-IV ALFRED reactor is simulated. • Effects on the mock-up of large seismic events are numerically investigated. • Impact forces on components are dominated by seismic high frequencies. • Impact forces due to sloshing are only marginal. This paper addresses one aspect of the safety of compact lead-cooled pool fast reactors. Under a seismic event, there is concern that the surface sloshing could compromise the integrity of some structures or components. We investigate this issue by means of computational modelling and simulation using the STAR-CCM + commercial software. In the first part, we simulate a partially filled vertical cylinder under harmonic forcing and quantitatively validate the modelling by comparison with experimental data of the free-surface height at different locations. Specifically, we capture with a very high precision a behavioral transition of the amplitude-frequency map near resonance. In the second part, the modelling is applied to a fast reactor mock-up in water. It is validated again by comparison with experimental data under harmonic forcing. The numerical mock-up is then subjected to four seismic events of increasing intensity. The free-surface height and the forces applied to the mock-up vessel are monitored. It is found that the forces applied to the vessel are strongly dominated by the highest frequency of the seismic acceleration. By applying a high filter cut at 1 Hz, the peak force is reduced by one order of magnitude but remains strongly related to the damped acceleration signal. Even then, sloshing forcing effects are observed but remain marginal.

Nuclear Engineering and DesignVol. 435
Openalex Percentile: Top 26%
Fluid Dynamics Simulations and Interactions
1.33
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Gen-IV pool reactors: Validation of sloshing CFD modelling and behavior under large seismic events — Manuela Profir, Vincent Moreau · Nuclear Engineering and Design (2025) | TGRS Research Map | TGRS