D. Matveev

Baumann, C., Romazanov, J., Matveev, D., Kirschner, A., Subba, F., Wiesen, S., … Linsmeier, C. (2026). Global tungsten erosion and migration modeling for the EU-DEMO with the ERO2.0 code. Nuclear Fusion, 66, 026010. https://doi.org/10.1088/1741-4326/ae27e5

Rode, S., Brezinsek, S., Groth, M., Kirschner, A., Matveev, D., Moser, L., … Wauters, T. (2024). Multi-staged ERO2.0 simulation of material erosion and deposition in recessed mirror assemblies in JET and ITER. Nuclear Fusion, 64(8), 086032. https://doi.org/10.1088/1741-4326/ad556d

Borodkina, I., Borodin, D., Douai, D., Romazanov, J., Pawelec, E., De La Cal, E., … Laguardia, L. (2024). Modelling of plasma facing component erosion, impurity migration, dust transport and melting processes at JET-ILW. Nuclear Fusion, 64(10), 106009. https://doi.org/10.1088/1741-4326/ad56a3

Brezinsek, S., Coenen, J. W., Schwartz-Selinger, T., Schmid, K., Kirschner, A., Hakola, A., … contributors, W. P. (2017). Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion, 57(11), 116041. https://doi.org/10.1088/1741-4326/aa796e

Buzi, L., De Temmerman, G., Matveev, D., Reinhart, M., Schwartz-Selinger, T., Rasinski, M., … Van Oost, G. (2017). Surface modifications and deuterium retention in polycrystalline and single crystal tungsten as a function of particle flux and temperature. Journal of Nuclear Materials, 495, 211-219. https://doi.org/10.1016/j.jnucmat.2017.08.026 (Original work published 2017)

Litnovsky, A., Hellwig, M., Matveev, D., Komm, M., van den Berg, M., De Temmerman, G., … Petersson, P. (2015). Optimization of tungsten castellated structures for the ITER divertor. Journal of Nuclear Materials, 463(Aug), 174-179. https://doi.org/10.1016/j.jnucmat.2014.11.009

Buzi, L., De Temmerman, G., Unterberg, B., Reinhart, M., Dittmar, T., Matveev, D., … Van Oost, G. (2015). Influence of tungsten microstructure and ion flux on deuterium plasma-induced surface modifications and deuterium retention. Journal of Nuclear Materials, 463(Aug), 320-324. https://doi.org/10.1016/j.jnucmat.2014.12.006

Hong, S. H., Bang, E. N., Lim, S. T., Lee, J. Y., Yang, S. J., Litnovsky, A., … Kim, G. H. (2014). Preliminary test results on tungsten tile with castellation structures in KSTAR. Fusion Engineering and Design, 89(7-8), 1704–1708. https://doi.org/http://dx.doi.org/10.1016/j.fusengdes.2014.01.033

Hong, S. H., Yu, Y., Kim, K. P., Bak, J. G., Park, H. J., Oh, Y. S., … Team, K. (2013). Plasma-Surface Interaction Activities in KSTAR. Fusion Science and Technology, 63, 88-93. Retrieved from http://epubs.ans.org/?p=fst:63:1T