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Publications by Ignas Mickus

Peer reviewed

Articles

[2]
I. Mickus and J. Dufek, "Does neutron clustering affect tally errors in Monte Carlo criticality calculations?," Annals of Nuclear Energy, vol. 155, 2021.
[3]
J. Dufek and I. Mickus, "Optimal time step length and statistics in Monte Carlo burnup simulations," Annals of Nuclear Energy, vol. 139, 2020.
[4]
I. Mickus, J. A. Roberts and J. Dufek, "Stochastic-deterministic response matrix method for reactor transients," Annals of Nuclear Energy, vol. 140, pp. 107103, 2020.
[5]
J. Wallenius et al., "Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications," Nuclear Engineering and Design, vol. 338, pp. 23-33, 2018.
[6]
I. Mickus and J. Dufek, "Optimal neutron population growth in accelerated Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 117, pp. 297-304, 2018.
[7]
I. Mickus, J. Dufek and K. Tuttelberg, "PERFORMANCE OF THE EXPLICIT EULER AND PREDICTOR-CORRECTOR-BASED COUPLING SCHEMES IN MONTE CARLO BURNUP CALCULATIONS OF FAST REACTORS," Nuclear Technology, vol. 191, no. 2, pp. 193-198, 2015.

Conference papers

[8]
K. W. Wong et al., "CFD STUDIES OF SEPARATE EFFECT FLOW ACCELERATED CORROSION AND EROSION (SEFACE) FACILITY FOR HEAVY LIQUID METAL," in Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables : United to Provide Carbon Neutral Power", ICONE 2023, 2023.
[10]
I. Mickus, J. A. Roberts and J. Dufek, "Application of response matrix method to transient simulations of nuclear systems," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 786-793.
[11]
G. Acharya et al., "Investigation of a self-actuated, gravity-driven shutdown system in a small lead-cooled reactor," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 1456-1463.
[12]
J. Dufek and I. Mickus, "Optimisation of Monte Carlo burnup simulations," in International Conference on Physics of Reactors : Transition to a Scalable Nuclear Future, PHYSOR 2020, 2020, pp. 804-810.
[13]
J. Wallenius, S. Bortot and I. Mickus, "Unprotected transients in sealer : A small lead-cooled reactor for commercial power production in Arctic Regions," in International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems, 2018, pp. 1437-1448.
[14]
I. Mickus et al., "Development of tall-3d test matrix for APROS code validation," in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, pp. 4562-4575.
[15]
I. Mickus, J. Lappalainen and P. Kudinov, "Validation of APROS Code Against Experimental Data from a Lead-Bismuth Eutectic Thermal-Hydraulic Loop," in Proceedings of ICAPP 2015, May 03-06, 2015 - Nice (France), 2015.
[16]
I. Mickus et al., "An Approach to Physics Based Surrogate Model Development for Application with IDPSA," in Probabilistic Safety Assessment and Management PSAM 12, June 2014, Honolulu, Hawaii, 2014.

Non-peer reviewed

Chapters in books

[17]
C. Geffray et al., "Verification and validation and uncertainty quantification," in Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, : Elsevier, 2018, pp. 383-405.

Theses

[18]
I. Mickus, "Towards Efficient Monte Carlo Calculations in Reactor Physics : Criticality, Kinetics and Burnup Problems," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-SCI-FOU, 2021:41, 2021.
[19]
M. Ignas, "Response Matrix Reloaded : for Monte Carlo Simulations in Reactor Physics," Licentiate thesis : KTH Royal Institute of Technology, TRITA-SCI-FOU, 54, 2019.

Reports

[20]
D. Grishchenko, I. Mickus and P. Kudinov, "Experimental activities report on TALL-3D," , 2015.
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