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Ignas Mickus
Ignas Mickus
Unknown affiliation
Verified email at kth.se
Title
Cited by
Cited by
Year
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
672018
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
242019
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
122017
Optimal neutron population growth in accelerated Monte Carlo criticality calculations
I Mickus, J Dufek
Annals of Nuclear Energy 117, 297-304, 2018
102018
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
92018
Preliminary Transient Analysis of SEALER
I Mickus, J Wallenius, S Bortot
proceedings of FR17, IAEA-CN-245-433, IAEA, 2017
62017
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
52014
Does neutron clustering affect tally errors in Monte Carlo criticality calculations?
I Mickus, J Dufek
Annals of Nuclear Energy 155, 108130, 2021
42021
Stochastic-deterministic response matrix method for reactor transients
I Mickus, JA Roberts, J Dufek
Annals of Nuclear Energy 140, 107103, 2020
42020
Optimal time step length and statistics in Monte Carlo burnup simulations
J Dufek, I Mickus
Annals of Nuclear Energy 139, 107244, 2020
42020
Towards Efficient Monte Carlo Calculations in Reactor Physics: Criticality, Kinetics and Burnup Problems
I Mickus
KTH Royal Institute of Technology, 2021
12021
SEALER-UK: A 55 MW (e) Lead Cooled Reactor for Commercial Power Production
J Wallenius, S Qvist, I Mickus, P Szakalos
12021
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
12021
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
12015
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
12015
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
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