BA2F02 Nuclear power plant analysis

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2020

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)

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)