| The TALL-3D facility design and commissioning tests for validation of coupled STH and CFD codes D Grishchenko, M Jeltsov, K Kööp, A Karbojian, W Villanueva, P Kudinov Nuclear Engineering and Design 290, 144-153, 2015 | 60 | 2015 |
| Comparison of different coupling CFD–STH approaches for pre-test analysis of a TALL-3D experiment A Papukchiev, M Jeltsov, K Kööp, P Kudinov, G Lerchl Nuclear Engineering and Design 290, 135-143, 2015 | 42 | 2015 |
| Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors G Bandini, M Polidori, A Gerschenfeld, D Pialla, S Li, WM Ma, P Kudinov, ... Nuclear Engineering and Design 281, 22-38, 2015 | 41 | 2015 |
| Development of a domain overlapping coupling methodology for STH/CFD analysis of heavy liquid metal thermal-hydraulics M Jeltsov, K Kööp, P Kudinov, W Villanueva NURETH-15, 2013 | 36 | 2013 |
| Safety analysis results of representative DEC accidental transients for the ALFRED reactor G Bandini, E Bubelis, M Schikorr, MH Stempnievicz, K Tucek, A Lázaro, ... | 30 | 2013 |
| Verification and validation and uncertainty quantification C Geffray, A Gerschenfeld, P Kudinov, I Mickus, M Jeltsov, K Kööp, ... Thermal hydraulics aspects of liquid metal cooled nuclear reactors, 383-405, 2019 | 27 | 2019 |
| TALL-3D open and blind benchmark on natural circulation instability D Grishchenko, A Papukchiev, C Liu, C Geffray, M Polidori, K Kööp, ... Nuclear Engineering and Design 358, 110386, 2020 | 21 | 2020 |
| Pre-test analysis for identification of natural circulation instabilities in TALL-3D facility K Kööp, M Jeltsov, D Grishchenko, P Kudinov Nuclear Engineering and Design 314, 110-120, 2017 | 11 | 2017 |
| Multiscale analysis of forced and natural convection including heat transfer phenomena in the TALL-3D experimental facility A Papukchiev, C Geffray, M Jeltsov, K Kööp, P Kudinov, D Grischenko NURETH-16: the 16th International Topical Meeting on Nuclear Reactor Thermal …, 2015 | 11 | 2015 |
| Feasibility Study for Connection Between IDPSA and conventional PSA Approach to Analysis of. Nordic type BWR's P Kudinov, S Galushin, S Raub, VA Phung, K Kööp, I Karanta, T Silvonen, ... NKS-DPSA Project, NKS-R, Report: NKS-315, 2014 | 9 | 2014 |
| An approach to validation of coupled CFD and system thermal-hydraulics codes M Jeltsov, F Cadinu, W Villanueva, A Karbojian, K Koop, P Kudinov | 7 | 2011 |
| An approach to physics based surrogate model development for application with IDPSA I Mickus, K Kööp, M Jeltsov, Y Vorobyev, W Villanueva, P Kudinov Probabilistic Safety Assessment and Management PSAM 12, June 2014, Honolulu …, 2014 | 5 | 2014 |
| Application of information technologies (genetic algorithms, neural networks, parallel calculations) in safety analysis of Nuclear Power Plants YB Vorobyev, P Kudinov, M Jeltsov, K Kööp, TV Nhat Proceedings of the Institute for System Programming of the RAS (Proceedings …, 2014 | 5 | 2014 |
| Development of TALL-3D facility design for validation of coupled STH and CFD codes M Jeltsov, K Kööp, D Grishchenko, A Karbojian, W Villanueva, P Kudinov NUTHOS-9, 2012 | 5 | 2012 |
| Characteristics of debris in the lower head of a BWR in different severe accident scenarios VA Phung, S Galushin, S Raub, A Goronovski, W Villanueva, K Kööp, ... Nuclear Engineering and Design 305, 359-370, 2016 | 4 | 2016 |
| Development of multi-scale simulation methodology for analysis of heavy liquid metal thermal hydraulics with coupled STH and CFD codes M Jeltsov, K Kööp, D Grishchenko, A Karbojian, W Villanueva, P Kudinov NUTHOS-9, 2012 | 4 | 2012 |
| Application of a system thermal-hydraulics code to development of validation process for coupled STH-CFD codes K Kööp KTH Royal Institute of Technology, 2018 | 3 | 2018 |
| Automation of RELAP5 input calibration and code validation using genetic algorithm VA Phung, K Kööp, D Grishchenko, Y Vorobyev, P Kudinov Nuclear Engineering and Design 300, 210-221, 2016 | 3 | 2016 |
| Prediction of coriu m debris characteristics in lower plenum of a Nordic BWR in different acciden t scenarios using MELCOR code VA Phung, S Galushin, S Raub, A Goronovski, W Villanueva, K Kööp, ... International Congresson Advances i n Nuclear Power Plants (ICAPP), France, 2015 | 2 | 2015 |
| Validation of a CFD code Star-CCM+ for liquid lead-bismuth eutectic thermal-hydraulics using TALL-3D experiment M Jeltsov, K Kööp, W Villanueva, D Grishchenko, P Kudinov The 10th International Topical Meeting on Nuclear Thermal-Hydraulics …, 2014 | 2 | 2014 |
