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Mikityuk, K.
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1

Simulation of flow and heat transfer in a differentially he..:

Sayed, M.A. ; Hadžiabdić, M. ; Dehbi, A...
International Journal of Thermal Sciences.  183 (2023)  - p. 107892 , 2023
Link: https://doi.org/10.1016/..
 
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2

Analysis of sodium boiling initiated by unprotected loss of..:

Bodi, J. ; Ponomarev, A. ; Mikityuk, K.
Nuclear Engineering and Design.  399 (2022)  - p. 112014 , 2022
Link: https://doi.org/10.1016/..
 
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3

CFD Simulation of Particle-Laden Flow in a 3D Differentiall..:

Sayed, M. A. ; Dehbi, A. ; Hadžiabić, M...
Flow, Turbulence and Combustion.  109 (2022)  4 - p. 961-990 , 2022
Link: https://doi.org/10.1007/..
 
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4

Interface Tracking Investigation of the Sliding Bubbles Eff..:

Wong, K. W. ; Bures, L. ; Mikityuk, K.
Nuclear Technology.  208 (2021)  8 - p. 1266-1278 , 2021
Link: https://doi.org/10.1080/..
 
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5

Optimization of multi-group energy structures for diffusion..:

Di Nora, V.A. ; Fridman, E. ; Nikitin, E...
Annals of Nuclear Energy.  155 (2021)  - p. 108183 , 2021
Link: https://doi.org/10.1016/..
 
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6

Optimization of multi-group energy structures for diffusion..:

Di Nora, V.A. ; Fridman, E. ; Nikitin, E...
Annals of Nuclear Energy.  163 (2021)  - p. 108541 , 2021
Link: https://doi.org/10.1016/..
 
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7

NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREME..:

Nikitin, E. ; Fridman, E. ; Mikityuk, K....
EPJ Web of Conferences.  247 (2021)  - p. 10017 , 2021
Link: https://doi.org/10.1051/..
 
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8

System codes benchmarking on a low sodium void effect SFR h..:

Bubelis, E. ; Tosello, A. ; Pfrang, W....
Nuclear Engineering and Design.  320 (2017)  - p. 325-345 , 2017
Link: https://doi.org/10.1016/..
 
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9

Solution of the OECD/NEA neutronic SFR benchmark with Serpe..:

Nikitin, E. ; Fridman, E. ; Mikityuk, K.
Annals of Nuclear Energy.  75 (2015)  - p. 492-497 , 2015
Link: https://doi.org/10.1016/..
 
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10

On the use of the SPH method in nodal diffusion analyses of..:

Nikitin, E. ; Fridman, E. ; Mikityuk, K.
Annals of Nuclear Energy.  85 (2015)  - p. 544-551 , 2015
Link: https://doi.org/10.1016/..
 
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11

Code assessment and modelling for Design Basis Accident Ana..:

Lázaro, A. ; Ammirabile, L. ; Bandini, G....
Nuclear Engineering and Design.  266 (2014)  - p. 1-16 , 2014
Link: https://doi.org/10.1016/..
 
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12

Code assessment and modelling for Design Basis Accident ana..:

Lazaro, A. ; Schikorr, M. ; Mikityuk, K....
Nuclear Engineering and Design.  277 (2014)  - p. 265-276 , 2014
Link: https://doi.org/10.1016/..
 
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13

The core design of ALFRED, a demonstrator for the European ..:

Grasso, G. ; Petrovich, C. ; Mattioli, D....
Nuclear Engineering and Design.  278 (2014)  - p. 287-301 , 2014
Link: https://doi.org/10.1016/..
 
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14

International benchmark on the natural convection test in P..:

Tenchine, D. ; Pialla, D. ; Fanning, T.H....
Nuclear Engineering and Design.  258 (2013)  - p. 189-198 , 2013
Link: https://doi.org/10.1016/..
 
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15

Analysis of selected Phenix EOL tests with the FAST code sy..:

Chenu, A. ; Adams, R. ; Mikityuk, K..
Annals of Nuclear Energy.  49 (2012)  - p. 182-190 , 2012
Link: https://doi.org/10.1016/..
 
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