| Status of severe accident studies at the end of the conceptual design of ASTRID: Feedback on mitigation features F Bertrand, N Marie, A Bachrata, V Brun-Magaud, JB Droin, X Manchon, ... Nuclear Engineering and Design 326, 55-64, 2018 | 44 | 2018 |
| Physical tool for unprotected loss of flow transient simulations in a sodium fast reactor JB Droin, N Marie, A Bachrata, F Bertrand, E Merle, JM Seiler Annals of nuclear energy 106, 195-210, 2017 | 35 | 2017 |
| Quench front progression in a superheated porous medium: experimental analysis and model development A Bachrata, F Fichot, G Repetto, M Quintard, J Fleurot | 30 | 2011 |
| Unprotected Loss of Flow simulation on ASTRID CFV-V3 reactor core A Bachrata, F Bertrand, D Lemasson Proceedings of ICAPP, 03-06, 2015 | 24 | 2015 |
| A physical tool for severe accident mitigation studies N Marie, A Bachrata, JM Seiler, F Barjot, A Marrel, S Gossé, F Bertrand Nuclear Engineering and Design 309, 224-235, 2016 | 15 | 2016 |
| Mitigation of severe accidents for SFR and associated event sequence assessment F Bertrand, A Bachrata, N Marie, S Kubo, Y Onoda, A Shibata, R Kubota, ... Nuclear Engineering and Design 372, 110993, 2021 | 13 | 2021 |
| A three-dimensional neutronics–Thermalhydraulics Unprotected Loss of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices A Bachrata, L Trotignon, P Sciora, M Saez Nuclear Engineering and Design 346, 1-9, 2019 | 13 | 2019 |
| France-Japan collaboration on the severe accident studies for ASTRID. Outcomes and future work program F Serre, F Bertrand, A Bachrata, N Marie, S Kubo, K Kamiyama, B Carluec, ... | 12 | 2017 |
| Quenching of a highly superheated porous medium by injection of water F Fichot, A Bachrata, G Repetto, J Fleurot, M Quintard Journal of Physics: Conference Series 395 (1), 012144, 2012 | 11 | 2012 |
| Design-oriented tool for Unprotected Loss Of Flow simulations in a Sodium Fast Reactor: Validation and application to stability analyses JB Droin, N Marie, F Bertrand, A Marrel, A Bachrata Nuclear Engineering and Design 361, 110550, 2020 | 10 | 2020 |
| Code simulation of quenching of a high temperature debris bed: Model improvement and validation with experimental results A Bachrata, F Fichot, G Repetto, M Quintard, J Fleurot International Conference on Nuclear Engineering 44991, 77-85, 2012 | 8 | 2012 |
| Application of the ASTEC V1 Code to the LIVE-L1 Experiment A Miassoedov, L Godin-Jacqmin, A Bachrata, T Cron, X Gaus-Liu, T Wenz Proceedings of the 2008 International Congress on Advances in Nuclear Power …, 2008 | 8 | 2008 |
| Simplified criteria for a comparison of the accidental behaviour of Gen IV nuclear reactors and of PWRS F Bertrand, N Marie, A Bachrata, JB Droin, X Manchon, T Le Meute, ... Nuclear Engineering and Design 372, 110962, 2021 | 7 | 2021 |
| A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors A Bachrata, F Bertrand, N Marie, F Serre Journal of Nuclear Engineering and Radiation Science 7 (3), 030801, 2021 | 6 | 2021 |
| Severe accident studies on the efficiency of mitigation devices in a SFR core with SIMMER code A Bachrata, F Bertrand, N Marie, A Edeline, R Kubota, K Kamiyama, ... Nuclear Engineering and Design 373, 111037, 2021 | 6 | 2021 |
| Coolability evaluation of debris bed on core catcher in a sodium-cooled fast reactor E Matsuo, K Sasa, K Koyama, H Yamano, S Kubo, E Hourcade, ... The Proceedings of the International Conference on Nuclear Engineering …, 2019 | 6 | 2019 |
| Reflooding of a severely damaged reactor core: Experimental analysis and modelling A Bachrata, F Fichot, G Repetto, M Quintard, J Fleurot Proceedings of ICONE-19 Conference, 19th International Conference on Nuclear …, 2011 | 6 | 2011 |
| Analysis of the LIVE-L1 experiment with the ASTEC V1. 3 code L Godin-Jacqmin, A Bachrata SARNET/ASTEC report, CEA/DEN/DTN/STRY/LMA/2007-031, 2007 | 6 | 2007 |
| Improvement of model for SIMMER code for SFR corium relocation studies A Bachrata, N Marie, F Bertrand, JB Droin International Journal of Physical and Mathematical Sciences 8 (3), 516-521, 2014 | 5 | 2014 |
| Modélisation du renoyage d'un cœur du réacteur nucléaire fortement dégradé A Bachrata Toulouse, INPT, 2012 | 5 | 2012 |
