Boiling flow visualization experiment scaled to divertor cooling conditions

• Presenting new FEDORA experiment, that enables direct visualization of boiling flow in conditions relevant to fusion divertor cooling channels. • Implementation of a similarity-based downscaling approach, using a surrogate fluid (R245fa), to scale down high-heat-flux divertor conditions. • Development of bubble detection algorithm to characterize bubble sizes under varying flow and heat-flux conditions. • Demonstration of the feasibility of obtaining local boiling parameters (bubble size distribution) needed to improve mechanistic boiling models in high-heat-flux CFD simulations. A dedicated experiment FEDORA (Fusion Experiment for Divertor Optimization Research Applications) has been constructed to visualize flow boiling at scaled fusion divertor conditions. Its main purpose is to obtain the information on local boiling parameters, needed for the development of mechanistic boiling models in Computational Fluid Dynamics (CFD) codes. Current boiling models, although grounded on realistic physical principles, still rely heavily on empirical correlations, particularly for boiling parameters such as nucleation site density, bubble departure diameter, and bubble departure frequency. Due to the harsh operating conditions in the water-cooled divertor plasma-facing components (high heat fluxes over 10 MW/m 2 , mean flow velocity of about 9 m/s), visualization of boiling in realistic cooling channels is not feasible. The proposed experiment addresses this challenge by employing a surrogate coolant, characterized by lower latent heat and saturation temperature. By analyzing key dimensionless numbers, the aim is to replicate boiling conditions to be similar to those in coolant channels of upcoming divertor designs. Distinctive features of the proposed experimental setup include visually transparent boiling channel, infra-red transparent window and a thin electrically heated foil. This setup allows simultaneous high-speed and high-resolution recording of boiling phenomena in the flow and measurement of temperature distribution on the heated surface. In this work, the design, similarity analysis and the first measurement results are presented, proving the concept of the visualization approach to understand the boiling heat transfer in divertor cooling channels.

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Publication Details

Journal
Fusion Engineering and Design
Published
2025-05-23
DOI
https://doi.org/10.1016/j.fusengdes.2025.115188
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.52

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Boiling flow visualization experiment scaled to divertor cooling conditions

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Fusion materials and technologies
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article

Boiling flow visualization experiment scaled to divertor cooling conditions

M. Richou, Matej Tekavčič, Boštjan Končar, Gregor Kozmus, Aljoša Gajšek
article en
1 citations

Abstract

• Presenting new FEDORA experiment, that enables direct visualization of boiling flow in conditions relevant to fusion divertor cooling channels. • Implementation of a similarity-based downscaling approach, using a surrogate fluid (R245fa), to scale down high-heat-flux divertor conditions. • Development of bubble detection algorithm to characterize bubble sizes under varying flow and heat-flux conditions. • Demonstration of the feasibility of obtaining local boiling parameters (bubble size distribution) needed to improve mechanistic boiling models in high-heat-flux CFD simulations. A dedicated experiment FEDORA (Fusion Experiment for Divertor Optimization Research Applications) has been constructed to visualize flow boiling at scaled fusion divertor conditions. Its main purpose is to obtain the information on local boiling parameters, needed for the development of mechanistic boiling models in Computational Fluid Dynamics (CFD) codes. Current boiling models, although grounded on realistic physical principles, still rely heavily on empirical correlations, particularly for boiling parameters such as nucleation site density, bubble departure diameter, and bubble departure frequency. Due to the harsh operating conditions in the water-cooled divertor plasma-facing components (high heat fluxes over 10 MW/m 2 , mean flow velocity of about 9 m/s), visualization of boiling in realistic cooling channels is not feasible. The proposed experiment addresses this challenge by employing a surrogate coolant, characterized by lower latent heat and saturation temperature. By analyzing key dimensionless numbers, the aim is to replicate boiling conditions to be similar to those in coolant channels of upcoming divertor designs. Distinctive features of the proposed experimental setup include visually transparent boiling channel, infra-red transparent window and a thin electrically heated foil. This setup allows simultaneous high-speed and high-resolution recording of boiling phenomena in the flow and measurement of temperature distribution on the heated surface. In this work, the design, similarity analysis and the first measurement results are presented, proving the concept of the visualization approach to understand the boiling heat transfer in divertor cooling channels.

Fusion Engineering and DesignVol. 218
University of Ljubljana (SI), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), Jožef Stefan Institute (SI), CEA Cadarache (FR)
EUROfusion, European Commission, Javna Agencija za Raziskovalno Dejavnost RS, Euratom Research and Training Programme
Affordable and clean energy
Openalex Percentile: Top 38%
Fusion materials and technologies
0.52
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