BA2F02 Nuclear power plant analysis

Research Output

2020

Architecture Design for NPP Co-Simulation Platform

Divshali, P., Hänninen, S., Laakso, P. & Korvola, T., 28 Feb 2020, VTT Technical Research Centre of Finland. 22 p. (VTT Technology; No. 371).

Research output: Book/ReportReport

Open Access

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

Extending thermal-hydraulic modelling capabilities of Apros into coiled geometries

Leskinen, J., Ylätalo, J. & Pettini, R., Feb 2020, In : Nuclear Engineering and Design. 357, 110429.

Research output: Contribution to journalArticleScientificpeer-review

Modeling of PANDA isolation condenser experiments with MELCOR and Apros

Sevón, T. & Hillberg, S., Feb 2020, In : Annals of Nuclear Energy. 136, 107014.

Research output: Contribution to journalArticleScientificpeer-review

2019

Containment model library of the Apros process simulation software: an overview of development and validation work

Silde, A., Ylijoki, J. & Ahtinen, E., 2019, In : Progress in Nuclear Energy. 116, p. 28-45 18 p.

Research output: Contribution to journalArticleScientificpeer-review

Open Access
1 Citation (Scopus)

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)
2008

Simulation of flows at supercritical pressures with a two-fluid code

Hänninen, M. & Kurki, J., 2008.

Research output: Contribution to conferenceConference articleScientific

Open Access
2007

Experimental and Numerical Studies of Liquid Dispersal from a Soft Projectile Impacting a Wall

Silde, A., Hostikka, S., Kankkunen, A., Hyvärinen, J. & Hakola, I., 2007, Proceedings: 19th International Conference on Structural Mechanics in Reactor Technology 2007, SMiRT 19. Vol. 3. p. 1535-1542 (Transactions of SMiRT, Vol. 19).

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

2005

Dynamic model of 5 kW SOFC CHP power plant

Saarinen, J., Halinen, M., Noponen, M., Ylijoki, J. & Kiviaho, J., 2005, p. 96.

Research output: Contribution to conferenceConference PosterScientific