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Chen, L., Fang, D., Villanueva, W., Zhao, W., Xiang, Y., Komlev, A. & Ma, W. (2026). Microscopic insights into the effect of surface wettability on melt infiltration in porous media: Experimental and simulation studies. Physics of fluids, 38(1), Article ID 012017.
Open this publication in new window or tab >>Microscopic insights into the effect of surface wettability on melt infiltration in porous media: Experimental and simulation studies
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2026 (English)In: Physics of fluids, ISSN 1070-6631, E-ISSN 1089-7666, Vol. 38, no 1, article id 012017Article in journal (Refereed) Published
Abstract [en]

The influence of particle surface wettability on melt infiltration in porous media is investigated by combining both experiments and simulations. Melt infiltration experiments are conducted by introducing molten tin-bismuth eutectic alloy (Sn-Bi) into preheated particle beds composed of 1.5 mm spherical particles of either copper (Cu) or tin-coated Cu (Sn-coated Cu). After solidification, the distribution of Sn-Bi within the particle beds is analyzed using scanning electron microscopy (SEM). To complement the experimental findings, three-dimensional (3D) pore-scale numerical simulations are carried out, allowing a direct comparison between the simulated melt distribution and SEM observations. The SEM analysis of the composite of the particle bed infiltrated by Sn-Bi reveals that at temperatures below 150 °C, the Cu particles exhibit poor wettability by Sn-Bi melt, characterized by a local contact angle of around 145°, whereas Sn-coated particles demonstrate enhanced wettability with a contact angle of approximately 65°. These observations are also supported by the 3D simulations, which show that higher wettability leads to smoother melt fronts and more pervasive infiltration, while lower wettability results in restricted melt infiltration. The findings highlight the critical role of particle surface wettability in governing melt infiltration, which is crucial for understanding the melt relocation behaviors in safety-critical systems and optimizing materials processing.

Place, publisher, year, edition, pages
AIP Publishing, 2026
National Category
Materials Engineering
Identifiers
urn:nbn:se:kth:diva-376521 (URN)10.1063/5.0308322 (DOI)2-s2.0-105028592151 (Scopus ID)
Note

QC 20260209

Available from: 2026-02-09 Created: 2026-02-09 Last updated: 2026-02-09Bibliographically approved
Xiang, Y., Fang, D., Komlev, A. A., Deng, Y., Chen, L. & Ma, W. (2024). A scoping investigation on debris bed formation with high-temperature melt simulant Fe-Sn. Applied Thermal Engineering, 257, 124405-124405, Article ID 124405.
Open this publication in new window or tab >>A scoping investigation on debris bed formation with high-temperature melt simulant Fe-Sn
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2024 (English)In: Applied Thermal Engineering, ISSN 1359-4311, E-ISSN 1873-5606, Vol. 257, p. 124405-124405, article id 124405Article in journal (Refereed) Published
Place, publisher, year, edition, pages
Elsevier BV, 2024
National Category
Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-357437 (URN)10.1016/j.applthermaleng.2024.124405 (DOI)001320143700001 ()2-s2.0-85203875440 (Scopus ID)
Note

QC 20241211

Available from: 2024-12-06 Created: 2024-12-06 Last updated: 2024-12-11Bibliographically approved
Deng, Y., Guo, Q., Xiang, Y., Fang, D., Komlev, A. A., Bechta, S. & Ma, W. (2024). An experimental study on the effect of coolant salinity on steam explosion. Annals of Nuclear Energy, 201, Article ID 110420.
Open this publication in new window or tab >>An experimental study on the effect of coolant salinity on steam explosion
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2024 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 201, article id 110420Article in journal (Refereed) Published
Abstract [en]

The steam explosion plays an essential role in the safety analysis of light water reactors (LWRs). Some studies have demonstrated that the occurrence of steam explosions is dependent on many factors such as melt and coolant temperatures, melt and coolant properties, non -condensable gases, etc. After the Fukushima accident, seawater as an emergency coolant and its impact on fuel coolant interactions are receiving attention. However, there is still little knowledge on the impact of seawater on steam explosion. The present study is intended to examine the effect of coolant salinity on steam explosion through a series of tests with single molten droplet falling in different coolant pools (DI water, and seawater at different salinities from 7.7 g/kg to 35 g/kg). The experimental results reveal that the salinity of coolant significantly influences the probability of spontaneous steam explosion of molten tin droplets. The probability of steam explosion generally increases with increasing salinity from 0 to 17.5 g/kg. The molten droplet in seawater experiences more pronounced deformation at same depth before the vapor film of the droplet collapses. What's more, the peak pressure generated by steam explosion in seawater is notably higher than that in DI water. The fragmentation of molten tin droplet after the explosion is enhanced accordingly.

Place, publisher, year, edition, pages
Elsevier BV, 2024
Keywords
Severe accident, Fuel -coolant interactions, Steam explosion, Seawater
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-345540 (URN)10.1016/j.anucene.2024.110420 (DOI)001197465800001 ()2-s2.0-85185716891 (Scopus ID)
Note

QC 20240415

Available from: 2024-04-15 Created: 2024-04-15 Last updated: 2024-12-03Bibliographically approved
Chen, L., Komlev, A. A., Ma, W., Bechta, S., Villanueva, W., Rangavittal, B. V., . . . Hoseyni, S. M. (2024). An experimental study on the impact of particle surface wettability on melt infiltration in particulate beds. Annals of Nuclear Energy, 206, Article ID 110664.
Open this publication in new window or tab >>An experimental study on the impact of particle surface wettability on melt infiltration in particulate beds
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2024 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 206, article id 110664Article in journal (Refereed) Published
Abstract [en]

Melt infiltration into porous media is an intriguing phenomenon that holds immense significance across various sciences and technologies. In this work, the problem of metallic melt infiltration in particulate beds is investigated for understanding and prediction of severe accident progression associated with a molten pool penetrating through an underlying debris bed which may form in the reactor core or in the lower head of a light water reactor. The present study aims to quantify the effect of particle surface's wettability on melt infiltration kinetics. For this purpose, two categories of experiment are conceived and carried out to measure the wettability of different material surfaces by melt and to characterize melt infiltration kinetics in one-dimensional particulate beds, respectively. The melt material is tin–bismuth eutectic alloy with a melting point of 139 °C. Copper (Cu), stainless steel (SS), Tin (Sn) and tin-coated stainless steel (Sn-coated SS) are chosen as materials of substrates and particles in wettability measurement and melt infiltration study. The particulate beds, packed with 1.5 mm spheres, are preheated to 200 °C before the melt infiltration begins. The experimental data of wettability measurement shows that the contact angles of liquid Sn-Bi eutectic on the above-mentioned material surfaces range from 79° to 135°. The results of melt infiltration tests confirm the significant effect of wettability on melt penetration kinetics. The capillary force plays a significant role in the initial infiltration of particulate beds. Specifically, a wettable particulate bed enhances the initial melt infiltration, whereas non-wettable beds hinder it.

Place, publisher, year, edition, pages
Elsevier BV, 2024
Keywords
Melt infiltration, Multi-phase flow, Porous media, Surface wettability
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-347296 (URN)10.1016/j.anucene.2024.110664 (DOI)001246740700001 ()2-s2.0-85194159792 (Scopus ID)
Note

QC 20240702

Available from: 2024-06-10 Created: 2024-06-10 Last updated: 2025-05-06Bibliographically approved
Chen, L., Xiang, Y., Zhao, L., Fang, D., Villanueva, W., Komlev, A. A., . . . Bechta, S. (2024). Modeling melt relocation with solidification and remelting using a coupled level-set and enthalpy-porosity method. Journal of Materials Research and Technology, 33, 9888-9897
Open this publication in new window or tab >>Modeling melt relocation with solidification and remelting using a coupled level-set and enthalpy-porosity method
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2024 (English)In: Journal of Materials Research and Technology, ISSN 2238-7854, E-ISSN 2214-0697, Vol. 33, p. 9888-9897Article in journal (Refereed) Published
Abstract [en]

A numerical model to simulate molten metal relocation with phase change is proposed, coupling the level-set method to track the metal-gas interface and an enthalpy-porosity model to handle phase changes between solid and liquid metal. This coupling simultaneously solves the evolution of the metal-gas interface and liquid-solid metal. The numerical model is validated by a melting experiment involving a Sn–Bi eutectic alloy on a copper substrate, wherein the alloy's transient morphology and spreading diameter are measured. The numerical simulation effectively replicates the observed melting and spreading behaviors of the metal on the solid surface. Further validations, including a melt infiltration simulation and experiment, are consistent with findings from previous research. These simulations affirm the model's capability and efficiency in accurately representing the dynamics of melt relocation across various geometries, even within complex porous structures.

Place, publisher, year, edition, pages
Elsevier BV, 2024
National Category
Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-357436 (URN)10.1016/j.jmrt.2024.12.025 (DOI)001375528800001 ()2-s2.0-85211062463 (Scopus ID)
Note

QC 20241210

Available from: 2024-12-06 Created: 2024-12-06 Last updated: 2025-05-06Bibliographically approved
Guo, Q., Deng, Y., Komlev, A. A., Ma, W. & Bechta, S. (2024). Oxidation of molten zirconium-containing droplet in water. Progress in nuclear energy (New series), 175, Article ID 105341.
Open this publication in new window or tab >>Oxidation of molten zirconium-containing droplet in water
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2024 (English)In: Progress in nuclear energy (New series), ISSN 0149-1970, E-ISSN 1878-4224, Vol. 175, article id 105341Article in journal (Refereed) Published
Abstract [en]

During a severe accident in light water reactors, the molten reactor core (corium) falls into a water pool in the form of a jet. Complex interactions may occur between the melt and coolant known as molten fuel-coolant interactions (FCI), including energetic coolant evaporation and metallic melt (e.g., Zr and Fe) oxidation. This may further lead to steam and hydrogen explosions, which are both substantial safety risks for nuclear power plants. The heat of reaction and hydrogen production during oxidation can influence the progress and severity of the accidents. For example, the reaction heat may prolong the liquid state of corium, potentially leading to highintensity explosions, whereas the generated hydrogen can create a combustible atmosphere, increasing the risk of hydrogen explosion. Therefore, this study evaluates the hydrogen production and oxidation degree of molten metallic droplets falling into a water pool to improve the FCI models for the risk evaluation of severe accident safety. The MISTEE-OX facility at KTH, which has been primarily built to study steam explosions is modified to investigate oxidation during FCI and provide experimental data on the oxidation behaviour of metallic droplets (Zr/Fe) quenched in a subcooled water pool. The dynamics of the falling droplets and generated bubbles are recorded using a high-speed camera, and the total volume of the bubbles is measured using a graduated cylinder. This study presents preliminary experimental results of the oxidation between Zr/Fe droplets and water, as well as recent improvements in measurement methods and facility upgrades. Our research findings are useful to enhance the knowledge of the oxidation process in FCI phenomena and validate the related mechanistic models in FCI codes.

Place, publisher, year, edition, pages
Elsevier BV, 2024
Keywords
Fuel -coolant interactions, Oxidation, Zirconium/iron, Hydrogen, Melt temperature
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-350797 (URN)10.1016/j.pnucene.2024.105341 (DOI)001264853600001 ()2-s2.0-85197057583 (Scopus ID)
Note

QC 20240722

Available from: 2024-07-22 Created: 2024-07-22 Last updated: 2024-07-22Bibliographically approved
Chen, L., Komlev, A. A., Ma, W. & Bechta, S. (2023). A Numerical Study of Melt Penetration into a Particulate Bed. In: Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023: . Paper presented at 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, Washington, United States of America, Aug 20 2023 - Aug 25 2023 (pp. 660-669). American Nuclear Society
Open this publication in new window or tab >>A Numerical Study of Melt Penetration into a Particulate Bed
2023 (English)In: Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, American Nuclear Society , 2023, p. 660-669Conference paper, Published paper (Refereed)
Abstract [en]

Motivated by a need to characterise debris remelting phenomena which may occur during the progression of a severe accident in light water reactors, experimental studies on melt penetration in a debris bed have been carried out at KTH. To help understand experimental observations and obtain more detailed information of melt infiltration inside debris beds, a numerical study on melt penetration in particulate beds is presented in this paper. The Level set method was adopted through the COMSOL Multi-physics platform to track the melt-gas multiphase flow in particulate beds. The numerical model is primarily validated against available experiments. Further simulation results show the bed's wettability significantly affects the dynamics of melt penetration in a preheated particulate bed when the capillary force is relatively higher than the inertial force. In addition, melt initially penetrates deeper and faster in wettable particulate beds.

Place, publisher, year, edition, pages
American Nuclear Society, 2023
Keywords
debris remelting, melt penetration, Multiphase flow, porous media, wettability
National Category
Energy Engineering Fluid Mechanics
Identifiers
urn:nbn:se:kth:diva-353504 (URN)10.13182/NURETH20-40219 (DOI)2-s2.0-85202975288 (Scopus ID)
Conference
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, Washington, United States of America, Aug 20 2023 - Aug 25 2023
Note

Part of ISBN 9780894487934

Available from: 2024-09-19 Created: 2024-09-19 Last updated: 2025-05-06Bibliographically approved
Xiang, Y., Liang, D., Komlev, A. A., Fang, D., Deng, Y., Zhao, L. & Ma, W. (2023). An experimental investigation on debris bed formation from fuel coolant interactions of metallic and oxidic melts. Applied Thermal Engineering, 233, Article ID 121186.
Open this publication in new window or tab >>An experimental investigation on debris bed formation from fuel coolant interactions of metallic and oxidic melts
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2023 (English)In: Applied Thermal Engineering, ISSN 1359-4311, E-ISSN 1873-5606, Vol. 233, article id 121186Article in journal (Refereed) Published
Abstract [en]

During postulated severe accidents in a light water reactor (LWR), the core melt (corium) may relocate to the lower head and fail the reactor pressure vessel (RPV). The corium is expected to undergo fuel coolant interactions (FCI) if the reactor cavity is flooded with water. Both FCI energetics and resulting debris bed coolability are of paramount importance to reactor safety, since the ex-vessel corium poses a threat to the containment integrity if steam explosion occurs or the debris bed is uncoolable, leading to release of radioactive fission products to the environment. The present study is intended to quantify the characteristics of a debris bed resulting from FCI, which are crucial to debris bed coolability. Different from the previous studies with only oxidic materials, various materials, including metallic ones of Sn, Sn-Bi and Zn as well as oxidic one of Bi2O3-WO3, were employed as the simulants of corium (mixture of UO2/ZrO2/Zr/Fe) in the present study to investigate the effects of melt materials, melt superheat and coolant subcooling on debris bed formation in a water pool. High-speed photography was applied to visualize melt jet breakup, droplets fragmentation, as well as fragments sedimentation on the pool floor. Other obtained data are debris bed shape (profile) and porosity, as well as morphology and size distri-bution of debris particles. The comparative results of various tests provided insights toward filling the knowledge gap on debris bed characteristics under different melt materials and compositions.

Place, publisher, year, edition, pages
Elsevier BV, 2023
Keywords
Fuel coolant interactions, Metallic melt, Oxidic melt, Melt jet fragmentation, Debris bed
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-335133 (URN)10.1016/j.applthermaleng.2023.121186 (DOI)001047363200001 ()2-s2.0-85165642996 (Scopus ID)
Note

QC 20230901

Available from: 2023-09-01 Created: 2023-09-01 Last updated: 2023-10-10Bibliographically approved
Xiang, Y., Komlev, A. A., Chen, Y., Ma, W., Villanueva, W., Konovalenko, A. & Bechta, S. (2023). Pre-test simulation and a scoping test for dryout and remelting phenomena of an in-vessel debris bed. Nuclear Engineering and Design, 403, Article ID 112143.
Open this publication in new window or tab >>Pre-test simulation and a scoping test for dryout and remelting phenomena of an in-vessel debris bed
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2023 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 403, article id 112143Article in journal (Refereed) Published
Abstract [en]

The present study is intended to investigate the dryout and remelting phenomena of a debris bed during the late phase of an in-vessel severe accident progression. The SIMECO-2 facility at KTH is adapted to conduct the experimental investigation. For selection of an appropriate debris bed in the facility, pre-test simulations are performed by using the COCOMO code to determine: (i) simulant materials of debris particles; (ii) debris bed particle diameters; (iii) configuration and geometry of the debris bed (e.g., shape, layers, dimensions). Candidate particulate beds packed with different mixtures of particles are identified and simulated to obtain their thermal hydraulics in the hemispherical slice test section with radius of 500 mm and width of 120 mm. Based on the simulation results, a particulate bed is chosen and loaded in the SIMECO-2 facility for a scoping investigation. FBG probes with multiple measurement points of each probe are employed to acquire the temperature field of the particulate bed inductively heated. A video recording is applied to detect the dryout and remelting phenomena. In the scoping test, the dryout phenomenon occur first at the elevation of 5 cm from the bed surface under the induction heating power of 14.8 kW, which are comparable with the data predicted by the COCOMO code (6 cm from the bed surface under the heating power of 13.8 kW) in the pre-test simulations.

Place, publisher, year, edition, pages
Elsevier BV, 2023
Keywords
Severe accident, Debris bed, Dryout, Remelting, COCOMO Code
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-324336 (URN)10.1016/j.nucengdes.2022.112143 (DOI)000923498200001 ()2-s2.0-85145964516 (Scopus ID)
Note

QC 20230228

Available from: 2023-02-28 Created: 2023-02-28 Last updated: 2023-02-28Bibliographically approved
Xiang, Y., Komlev, A. A., Chen, Y., Ma, W., Villanueva, W., Konovalenko, A. & Bechta, S. (2022). Pre-test simulations and a scoping test for dryout and remelting phenomena of an in-vessel debris beds. In: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19): . Paper presented at The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 29 August to 3 September 2021 in Brussels, Belgium.
Open this publication in new window or tab >>Pre-test simulations and a scoping test for dryout and remelting phenomena of an in-vessel debris beds
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2022 (English)In: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022Conference paper, Published paper (Refereed)
National Category
Other Physics Topics
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-312741 (URN)
Conference
The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 29 August to 3 September 2021 in Brussels, Belgium
Note

QC 20220620

Available from: 2022-05-22 Created: 2022-05-22 Last updated: 2022-12-13Bibliographically approved
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ORCID iD: ORCID iD iconorcid.org/0000-0001-8148-9423

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