Acknowledgement
Special thanks to the ATLAS and PKL experimental teams and the respective OECD/NEA ATLAS3 and ETHARINUS projects.
References
- WENRA, RHWG guidance document, issue F: design extension of existing reactors, in: Guidance for the WENRA Safety Reference Levels for Existing Reactors in Their Update in Relation to Lessons Learned from the TEPCO Fukushima Dai-Ichi Accident, 2014, p. 2014.
- SSR-2/1, Safety of Nuclear Power Plants: Design, Specific Safety Requirements, vol. 1, IAEA, 2016. Revision.
- C. Queral, J. Gonzalez-Cadelo, G. Jimenez, E. Villalba, Accident management actions in an upper-head small-break loss-of-coolant accident with high-pressure safety injection failed, Nuclear Technology 175 (2011).
- T. Takeda, Summary data report of ROSA/LSTF experiment SB-PV-07 - 1% pressure vessel top break LOCA with accident management actions and gas inflow, in: JAEA-Data/Code 2018, JAEA, 2018, 003.
- T. Takeda, Summary Data Report of ROSA/LSTF Experiment SB-PV-09 on PWR 1.9% Pressure Vessel Top Small Break LOCA with SG Depressurization and Gas Inflow, JAEA, 2021.
- Description Report of ATLAS Facility and Instrumentation, Korea Atomic Energy Research Institute, 2018. KAERI/TR-7218/2018.
- R. Guneysu, H. Kremin, Description of the PKL Test Facility, NTCTP-G/2007/en/0010, 2007.
- Y. Park, Quick-look report on the OECD-ATLAS2 B5.1 test: counterpart test for 1% SBLOCA at reactor pressure vessel top of LSTF with accident management actions and gas inflow, in: OECD-ATLAS2-QLR-20-03, KAERI, 2020.
- L. Dennhardt, S. Schollenberger, PKL III J1.1 - SB-LOCA of 1.9 % in the Upper Head, D02-ARV-01-192-258, 2022.
- Equipe CATHARE, CATHARE V2.5_3/mod8.1, SMTH/LMDS/EM/2002_067, 2018.
- A. Kovtonyuk1, M. Havet, T. de Laet, J. Nam, A. Bousbia Salah, R. Leung, N. Alyammahi, H. Austregesilo, S. Buchholz, Zh. Li, K.-H. Kang, S.W. Bae, Y. Park, M.K. Cho, P. Hellings, V. Corda, E. Cascioli, V. Jammot, J. Freixa, C. Berna Escriche, M. Lorduy, S. Gallardo, G. Verdu, D. Blanco, J.L. Munoz-Cobo, A. Escriva, R. Harrington, Analytical benchmark on OECD/NEA ATLAS-2 test B5.1, in: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-19, Brussels, Belgium, March 6 - 11, 2022.
- A. Bousbia Salah, J. Vlassenbroeck, H. Austregesilo, Experimental and analytical assessment of natural circulation interruption phenomenon in the LSTF and PKL test facilities, Nuclear Technology journal 192 (2015).