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Joona Kurki

  • Phone+358405769400
20082020

Research output per year

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Research Output

Critical flow prediction by system codes – Recent analyses made within the FONESYS network

Lanfredini, M., Bestion, D., D'Auria, F., Aksan, N., Fillion, P., Gaillard, P., Heo, J., Karppinen, I., Kim, K. D., Kurki, J., Liu, L., Shen, A., Vacher, J. L. & Wang, D., Sep 2020, In : Nuclear Engineering and Design. 366, 110731.

Research output: Contribution to journalArticleScientificpeer-review

  • Critical flow prediction by system codes - Recent analyses made within the FONESYS network

    Lanfredini, M., Bestion, D., D'Auria, F., Aksan, N., Fillion, P., Gaillard, P., Heo, J., Karppinen, I., Kim, K. D., Kurki, J., Lifang, L., Shen, A., Vacher, J. L. & Wang, D., 1 Jan 2019, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 20192019. American Nuclear Society ANS, p. 2274-2287 14 p.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

  • Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: PREMIUM benchmark

    Skorek, T., de Crécy, A., Kovtonyuk, A., Petruzzi, A., Mendizábal, R., de Alfonso, E., Reventós, F., Freixa, J., Sarrette, C., Kyncl, M., Pernica, R., Baccou, J., Fouet, F., Probst, P., Chung, B. D., Tram, T. T., Oh, D. Y., Gusev, A., Falkov, A., Shvestov, Y. & 10 others, Li, D., Liu, X., Zhang, J., Alku, T., Kurki, J., Jäger, W., Sánchez, V., Wicaksono, D., Zerkak, O. & Pautz, A., 1 Dec 2019, In : Nuclear Engineering and Design. 354, 110199.

    Research output: Contribution to journalArticleScientificpeer-review

  • 2 Citations (Scopus)

    Comprehensive and systematic validation of independent safety analysis tools (COVA)

    Hillberg, S., Karppinen, I., Silde, A., Kolehmainen, J., Dorval, E., Leskinen, J., Kurki, J., Alku, T., Lauerma, S., Skripnikov, D. & Hovi, T., 2017, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Interim Report. VTT Technical Research Centre of Finland, p. 215-222 (VTT Technology, Vol. 294).

    Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

    Open Access

    Statistical analysis of fuel failures in large break loss-of-coolant accident (LBLOCA) in EPR type nuclear power plant

    Arkoma, A., Hänninen, M., Rantamäki, K., Kurki, J. & Hämäläinen, A., 2015, In : Nuclear Engineering and Design. 285, p. 1-14

    Research output: Contribution to journalArticleScientificpeer-review

    Open Access
  • 14 Citations (Scopus)