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1

FAST: An advanced code system for fast reactor transient analysis

Konstantin Mikityuk, Sandro Pelloni, Paul Coddington, Evaldas Bubelis, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2005

Language:

english

File:

PDF, 371 KB

english, 2005

2

Heat transfer to liquid metal: Review of data and correlations for tube bundles

Konstantin Mikityuk

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.27 MB

english, 2009

3

Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel

Petr Petkevich, Konstantin Mikityuk, Paul Coddington, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2007

Language:

english

File:

PDF, 803 KB

english, 2007

4

Verification of the TRACE code against the MEGAPIE transient data

Evaldas Bubelis, Paul Coddington, Konstantin Mikityuk

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 882 KB

english, 2008

5

Development and benchmarking of a mechanical model for GFR plate-type fuel

Petr Petkevich, Konstantin Mikityuk, Paul Coddington, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 840 KB

english, 2009

6

EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors

Jiri Krepel, Sandro Pelloni, Konstantin Mikityuk, Paul Coddington

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 1.43 MB

english, 2009

7

Fuel cycle advantages and dynamics features of liquid fueled MSR

Křepel, Jiří, Hombourger, Boris, Fiorina, Carlo, Mikityuk, Konstantin, Rohde, Ulrich, Kliem, Sören, Pautz, Andreas

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 2.24 MB

english, 2014

8

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory - A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

Fiorina, Carlo, Aufiero, Manuele, Pelloni, Sandro, Mikityuk, Konstantin

Year:

2014

Language:

english

File:

PDF, 1.19 MB

english, 2014

9

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Hombourger, Boris A., Krepel, Jirí, Mikityuk, Konstantin, Pautz, Andreas

Journal:

Journal of Nuclear Engineering and Radiation Science

Year:

2015

Language:

english

File:

PDF, 1.28 MB

english, 2015

10

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security - Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

Křepel, Jiři, Bykov, Valentyn, Mikityuk, Konstantin, Hombourger, Boris, Fiorina, Carlo, Pautz, Andreas

Year:

2014

Language:

english

File:

PDF, 1.51 MB

english, 2014

11

TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods

Aaron Epiney, Konstantin Mikityuk, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 1.24 MB

english, 2010

12

Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle

Kaichao Sun, Jiri Krepel, Konstantin Mikityuk, Sandro Pelloni, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2011

Language:

english

File:

PDF, 1.49 MB

english, 2011

13

Analysis of radioactivity releases in the MEGAPIE reference accident

Konstantin Mikityuk, Paul Coddington, Friedrich Gröschel

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 855 KB

english, 2008

14

GFR equilibrium cycle analysis with the EQL3D procedure

Jiri Krepel, Sandro Pelloni, Konstantin Mikityuk, Paul Coddington

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 3.42 MB

english, 2010

15

Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions

Aaron Epiney, Konstantin Mikityuk, Rakesh Chawla

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 2.13 MB

english, 2010

16

A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors

Sandro Pelloni, Konstantin Mikityuk

Journal:

Annals of Nuclear Energy

Year:

2011

Language:

english

File:

PDF, 2.44 MB

english, 2011

17

Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX

Alessandro Marinoni, Gaetan Girardin, Konstantin Mikityuk

Journal:

Annals of Nuclear Energy

Year:

2012

Language:

english

File:

PDF, 751 KB

english, 2012

18

Gas cooled fast reactor research in Europe

Richard Stainsby, Karen Peers, Colin Mitchell, Christian Poette, Konstantin Mikityuk, Joe Somers

Journal:

Nuclear Engineering and Design

Year:

2011

Language:

english

File:

PDF, 1.30 MB

english, 2011

19

Comparison of open and closed U–Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure

Jiri Krepel, Sandro Pelloni, Konstantin Mikityuk

Journal:

Nuclear Engineering and Design

Year:

2012

Language:

english

File:

PDF, 1.37 MB

english, 2012

20

Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure

Fiorina, Carlo, Krepel, Jiri, Cammi, Antonio, Franceschini, Fausto, Mikityuk, Konstantin, Ricotti, Marco Enrico

Journal:

Annals of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 2.51 MB

english, 2013

21

A neutronics study for improving the safety and performance parameters of a 3600MWth Sodium-cooled Fast Reactor

Sun, Kaichao, Krepel, Jiri, Mikityuk, Konstantin, Chawla, Rakesh

Journal:

Annals of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 2.61 MB

english, 2013

22

Investigation of the MSFR core physics and fuel cycle characteristics

Fiorina, Carlo, Aufiero, Manuele, Cammi, Antonio, Franceschini, Fausto, Krepel, Jiri, Luzzi, Lelio, Mikityuk, Konstantin, Ricotti, Marco Enrico

Journal:

Progress in Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 2.31 MB

english, 2013

23

Development of a Drift-flux Model for Heavy Liquid Metal/Gas Flow

MIKITYUK, Konstantin, CODDINGTON, Paul, CHAWLA, Rakesh

Journal:

Journal of Nuclear Science and Technology

Year:

2005

Language:

english

File:

PDF, 399 KB

english, 2005

24

Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor

Perkó, Zoltán, Pelloni, Sandro, Mikityuk, Konstantin, Křepel, Jiri, Szieberth, Máté, Gaëtan, Girardin, Vrban, Branislav, Lüley, Jakub, Čerba, Štefan, Halász, Máté, Fehér, Sándor, Reiss, Tibor, Leen Kl

Journal:

Progress in Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 4.92 MB

english, 2015

25

Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels

Zhang, Youpeng, Mikityuk, Konstantin

Journal:

Annals of Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 2.16 MB

english, 2015

26

Gas Cooled Fast Reactor Research and Development in the European Union

Stainsby, Richard, Peers, Karen, Mitchell, Colin, Poette, Christian, Mikityuk, Konstantin, Somers, Joe

Journal:

Science and Technology of Nuclear Installations

Year:

2009

Language:

english

File:

PDF, 1.03 MB

english, 2009

27

GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors

Fiorina, Carlo, Clifford, Ivor, Aufiero, Manuele, Mikityuk, Konstantin

Journal:

Nuclear Engineering and Design

Year:

2015

Language:

english

File:

PDF, 3.10 MB

english, 2015

28

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems - Modeling of Sodium Two-Phase Flow With the TRACE Code

Chenu, Aurelia, Mikityuk, Konstantin, Chawla, Rakesh

Year:

2009

Language:

english

File:

PDF, 362 KB

english, 2009

29

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition - A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter

Fiorina, Carlo, Mikityuk, Konstantin, Křepel, Jiři

Year:

2014

Language:

english

File:

PDF, 808 KB

english, 2014

30

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles - Analysis of the MSFR Core Neutronics Adopting Different Neutron Transport Models

Fiorina, Carlo, Aufiero, Manuele, Cammi, Antonio, Guerrieri, Claudia, Krepel, Jiri, Luzzi, Lelio, Mikityuk, Konstantin, Ricotti, Marco Enrico

Year:

2012

Language:

english

File:

PDF, 1.40 MB

english, 2012

31

Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data

Brankov, Vladimir, Khvostov, Grigori, Mikityuk, Konstantin, Pautz, Andreas, Wiesenack, Wolfgang

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 1.74 MB

english, 2016

32

Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform

Fiorina, Carlo, Kerkar, Nordine, Mikityuk, Konstantin, Rubiolo, Pablo, Pautz, Andreas

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.75 MB

english, 2016

33

Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor

Fiorina, Carlo, Cammi, Antonio, Luzzi, Lelio, Mikityuk, Konstantin, Ninokata, Hisashi, Ricotti, Marco E

Journal:

Journal of Physics Conference Series

Year:

2014

Language:

english

File:

PDF, 1.07 MB

english, 2014

34

Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels

Brankov, Vladimir, Khvostov, Grigori, Mikityuk, Konstantin, Pautz, Andreas, Restani, Renato, Abolhassani, Sousan, Ledergerber, Guido, Wiesenack, Wolfgang

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 2.23 MB

english, 2016

35

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications - Allegro: The European Gas Fast Reactor Demonstrator Project

Poette, Christian, Brun-Magaud, Valérie, Morin, Franck, Pignatel, Jean-François, Stainsby, Richard, Mikityuk, Konstantin

Year:

2009

Language:

english

File:

PDF, 468 KB

english, 2009

36

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition - Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Hombourger, Boris A., Křepel, Jiři, Mikityuk, Konstantin, Pautz, Andreas

Year:

2014

Language:

english

File:

PDF, 2.73 MB

english, 2014

37

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co - Preliminary Analysis of the MSFR Fuel Cycle Using Modified-EQL3D Procedure

Fiorina, Carlo, Cammi, Antonio, Krepel, Jiri, Mikityuk, Konstantin, Ricotti, Marco Enrico

Year:

2012

Language:

english

File:

PDF, 1002 KB

english, 2012

38

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems - FAST Code System: Review of Recent Developments and Near-Future Plans

Mikityuk, Konstantin

Year:

2009

Language:

english

File:

PDF, 901 KB

english, 2009

39

FAST Code System: Review of Recent Developments and Near-Future Plans

Mikityuk, Konstantin, Krepel, Jiri, Pelloni, Sandro, Chenu, Aurelia, Petkevich, Petr, Chawla, Rakesh

Journal:

Journal of Engineering for Gas Turbines and Power

Year:

2010

Language:

english

File:

PDF, 1.57 MB

english, 2010

40

Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study for Improving the Response of a 3600 MW(Thermal) SFR Core to an Unprotected Loss-of-Flow Accident

Sun, Kaichao, Chenu, Aurelia, Krepel, Jiri, Mikityuk, Konstantin, Chawla, Rakesh

Journal:

Nuclear Technology

Year:

2013

Language:

english

File:

PDF, 1.62 MB

english, 2013

41

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems - Three-Dimensional Core Behaviour Analysis of the Gas-Cooled Fast Reactor (GFR) During Hypothetical Control Assembly Withdrawal Accidents

Girardin, Gaëtan, Blanchet, David, Mikityuk, Konstantin, Rimpault, Gérald, Chawla, Rakesh

Year:

2009

Language:

english

File:

PDF, 496 KB

english, 2009

42

Analytical solutions to a coupled fluid dynamics and neutron transport problem with application to GeN-Foam verification

de Oliveira, Rodrigo G.G., Mikityuk, Konstantin

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 807 KB

english, 2018

43

Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor

Nuria, García-Herranz, Anne-Laurène, Panadero, Ana, Martinez, Sandro, Pelloni, Konstantin, Mikityuk, Andreas, Pautz, Plompen, A., Hambsch, F.-J., Schillebeeckx, P., Mondelaers, W., Heyse, J., Kopecky,

Journal:

EPJ Web of Conferences

Year:

2017

Language:

english

File:

PDF, 552 KB

english, 2017

44

[American Institute of Aeronautics and Astronautics AIAA Scitech 2020 Forum - Orlando, FL ()] AIAA Scitech 2020 Forum - On the prediction of turbulent kinetic energy in channel flow using wall-modeled large eddy simulations

Sayed, Mohamed, Hadziabdic, Muhamed, Dehbi, Abdelouahab, Niceno, Bojan, Mikityuk, Konstantin

Language:

english

File:

PDF, 2.19 MB

english

45

[American Institute of Aeronautics and Astronautics AIAA Scitech 2020 Forum - Orlando, FL ()] AIAA Scitech 2020 Forum - Correction: On the prediction of turbulent kinetic energy in channel flow using wall-modeled large eddy simulations

Sayed, Mohamed, Hadziabdic, Muhamed, Dehbi, Abdelouahab, Niceno, Bojan, Mikityuk, Konstantin

File:

PDF, 303 KB

46

Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems

Mikityuk, Konstantin, Ammirabile, Luca, Forni, Massimo, Jagielski, Jacek, Girault, Nathalie, Horvath, Akos, Kloosterman, Jan-Leen, Tarantino, Mariano, Vasile, Alfredo, Garbil, R., Davies, C., Diaconu,

Journal:

EPJ Nuclear Sciences & Technologies

Year:

2020

File:

PDF, 2.61 MB

2020