Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications J Wallenius, S Qvist, I Mickus, S Bortot, P Szakalos, J Ejenstam Nuclear Engineering and Design 338, 23-33, 2018 | 67 | 2018 |
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 | 24 | 2019 |
SEALER: a small lead-cooled reactor for power production in the Canadian Arctic J Wallenius, S Qvist, I Mickus, S Bortot, J Ejenstam, P Szakalos | 12 | 2017 |
Optimal neutron population growth in accelerated Monte Carlo criticality calculations I Mickus, J Dufek Annals of Nuclear Energy 117, 297-304, 2018 | 10 | 2018 |
Unprotected transients in SEALER: A small lead-cooled reactor for commercial power production in Arctic regions J Wallenius, S Bortot, I Mickus Proc. PHYSOR, 2018 | 9 | 2018 |
Preliminary Transient Analysis of SEALER I Mickus, J Wallenius, S Bortot proceedings of FR17, IAEA-CN-245-433, IAEA, 2017 | 6 | 2017 |
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 |
Does neutron clustering affect tally errors in Monte Carlo criticality calculations? I Mickus, J Dufek Annals of Nuclear Energy 155, 108130, 2021 | 4 | 2021 |
Stochastic-deterministic response matrix method for reactor transients I Mickus, JA Roberts, J Dufek Annals of Nuclear Energy 140, 107103, 2020 | 4 | 2020 |
Optimal time step length and statistics in Monte Carlo burnup simulations J Dufek, I Mickus Annals of Nuclear Energy 139, 107244, 2020 | 4 | 2020 |
Towards Efficient Monte Carlo Calculations in Reactor Physics: Criticality, Kinetics and Burnup Problems I Mickus KTH Royal Institute of Technology, 2021 | 1 | 2021 |
SEALER-UK: A 55 MW (e) Lead Cooled Reactor for Commercial Power Production J Wallenius, S Qvist, I Mickus, P Szakalos | 1 | 2021 |
Investigation of a self-actuated, gravity-driven shutdown system in a small lead-cooled reactor G Acharya, F Dehlin, S Bortot, I Mickus EPJ Web of Conferences 247, 07007, 2021 | 1 | 2021 |
Development of tall-3d test matrix for APROS code validation I Mickus, K Kööp, M Jeltsov, D Grishchenko, P Kudinov, J Lappalainen 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2015 | 1 | 2015 |
Validation of APROS Code Against Experimental Data from a Lead-Bismuth Eutectic Thermal-Hydraulic Loop I Mickus, J Lappalainen, P Kudinov Proceedings of ICAPP 2015, 03-06, 2015 | 1 | 2015 |
Hydrodynamic design of the Separate Effect test facility for Flow-Accelerated Corrosion and Erosion (SEFACE) studies in liquid lead KW Wong, I Mickus, N Torkelson, S Vasudevan, H Li, D Grishchenko, ... Nuclear Engineering and Design 417, 112852, 2024 | | 2024 |
CFD STUDIES OF SEPARATE EFFECT FLOW ACCELERATED CORROSION AND EROSION (SEFACE) FACILITY FOR HEAVY LIQUID METAL KW Wong, I Mickus, S Vasudevan, H Li, D Grishchenko, P Kudinov The Proceedings of the International Conference on Nuclear Engineering …, 2023 | | 2023 |
Implementation of an autonomous reactivity control system in a small lead-cooled fast reactor F Dehlin, G Acharya, S Bortot, I Mickus EPJ Web of Conferences 247, 07006, 2021 | | 2021 |
APPLICATION OF RESPONSE MATRIX METHOD TO TRANSIENT SIMULATIONS OF NUCLEAR SYSTEMS I Mickus, JA Roberts, J Dufek PHYSOR 2020, 2020 | | 2020 |
OPTIMISATION OF MONTE CARLO BURNUP SIMULATIONS J Dufek, I Mickus PHYSOR 2020, 2020 | | 2020 |