Experimental study on natural circulation cooling system for core catcher with downward-facing heating channel

Core catchers are severe accident mitigation devices designed to prevent containment failure in nuclear power plants. In Korea, certain export-oriented nuclear reactors have adopted the PECS (Passive Ex-vessel corium retaining and Cooling System) core catcher design. This study investigates the cooling performance of this conceptually designed core catcher, PECS, using a scaled experimental facility, VPEX (Variable PECS EXperimental facility). The results showed that the cooling performance was satisfactory at an average heat flux value of 232 kW/m2, which is 1.75 times higher than predicted heat flux value. Furthermore, hydraulic and heat transfer characteristics for large-scale downward-facing heating channels were analyzed. It was observed that the large-scale facility exhibited relatively low heat transfer coefficient values compared to common laboratory scale facilities. Lower inlet pressures and less subcooling enhanced natural circulation mass flow rates and void fractions. Variations in inlet pressure, subcooling, or heat flux had minimal impacts on surface heat transfer characteristics such as boiling curves or heat transfer coefficients. Based on these experimental findings, the NCir (Natural Circulation calculator) analysis code was developed. The Wallis model provided the most accurate predictions for void fraction and natural circulation mass flow rate calculations. The experimental results and prediction code have potential applications in future PECS analyses. Additionally, they serve as fundamental data for large-scale facilities with downward-facing heating structures similar to VPEX.

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-08-09
DOI
https://doi.org/10.1016/j.net.2025.103845
Primary Topic
Nuclear Engineering Thermal-Hydraulics
Type
article
Field-Weighted Citation Impact
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article

Experimental study on natural circulation cooling system for core catcher with downward-facing heating channel

Seokgyu Jeong, Jun-young Kang, Byeonghee Lee, Jin Hyeok Kim et al.
Nuclear Engineering and Technology
Nuclear Engineering Thermal-Hydraulics
article

Experimental study on natural circulation cooling system for core catcher with downward-facing heating channel

Seokgyu Jeong, Jun-young Kang, Byeonghee Lee, Jin Hyeok Kim, Seong Ho Hong, Chang Wan Kang
article en

Abstract

Core catchers are severe accident mitigation devices designed to prevent containment failure in nuclear power plants. In Korea, certain export-oriented nuclear reactors have adopted the PECS (Passive Ex-vessel corium retaining and Cooling System) core catcher design. This study investigates the cooling performance of this conceptually designed core catcher, PECS, using a scaled experimental facility, VPEX (Variable PECS EXperimental facility). The results showed that the cooling performance was satisfactory at an average heat flux value of 232 kW/m2, which is 1.75 times higher than predicted heat flux value. Furthermore, hydraulic and heat transfer characteristics for large-scale downward-facing heating channels were analyzed. It was observed that the large-scale facility exhibited relatively low heat transfer coefficient values compared to common laboratory scale facilities. Lower inlet pressures and less subcooling enhanced natural circulation mass flow rates and void fractions. Variations in inlet pressure, subcooling, or heat flux had minimal impacts on surface heat transfer characteristics such as boiling curves or heat transfer coefficients. Based on these experimental findings, the NCir (Natural Circulation calculator) analysis code was developed. The Wallis model provided the most accurate predictions for void fraction and natural circulation mass flow rate calculations. The experimental results and prediction code have potential applications in future PECS analyses. Additionally, they serve as fundamental data for large-scale facilities with downward-facing heating structures similar to VPEX.

Nuclear Engineering and TechnologyVol. 57(12)
Ministry of Trade, Industry and Energy, Korea Institute of Energy Technology Evaluation and Planning
Openalex Percentile: Top 72%
Nuclear Engineering Thermal-Hydraulics
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