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Publikationer av Ignas Mickus

Refereegranskade

Artiklar

[2]
I. Mickus och J. Dufek, "Does neutron clustering affect tally errors in Monte Carlo criticality calculations?," Annals of Nuclear Energy, vol. 155, 2021.
[3]
J. Dufek och 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 och J. Dufek, "Stochastic-deterministic response matrix method for reactor transients," Annals of Nuclear Energy, vol. 140, s. 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, s. 23-33, 2018.
[6]
I. Mickus och J. Dufek, "Optimal neutron population growth in accelerated Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 117, s. 297-304, 2018.
[7]
I. Mickus, J. Dufek och 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, s. 193-198, 2015.

Konferensbidrag

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

Icke refereegranskade

Kapitel i böcker

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

Avhandlingar

[18]
I. Mickus, "Towards Efficient Monte Carlo Calculations in Reactor Physics : Criticality, Kinetics and Burnup Problems," Doktorsavhandling 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," Licentiatavhandling : KTH Royal Institute of Technology, TRITA-SCI-FOU, 54, 2019.

Rapporter

[20]
D. Grishchenko, I. Mickus och P. Kudinov, "Experimental activities report on TALL-3D," , 2015.
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2024-04-25 00:34:50