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Konstantin Mikityuk

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Publications associées (25)

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Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing-Part II: Methodology application

Konstantin Mikityuk, Vincenzo Anthony Di Nora

Part I of this study introduced a novel methodology for the optimization of energy group structures to be used in diffusion calculations of Sodium cooled Fast Reactors. The goal of the optimization is to speed up calculations, particularly in transient ana ...

2021

TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

In the framework of PSI's FAST code system, the thermal-hydraulic code TRACE is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicab ...

Elsevier Science B.V.2009

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

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The sodium-cooled fast reactor (SFR), as a fast neutron spectrum system, is characterized by several performance advantages. In particular, the long-term operation of an SFR core in a closed fuel cycle will lead to an equilibrium state, where both reactivi ...

Amer Nuclear Soc2013

Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor

Rakesh Chawla, Konstantin Mikityuk, Gaëtan Girardin

The present paper is related to the design and neutronic characterization of the principal control assembly system for the reference large (2400 MWth) Generation IV gas-cooled fast reactor (GFR), which makes use of ceramic-ceramic (CERCER) plate-type fuel- ...

Elsevier Science Ltd.2008

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

Rakesh Chawla, Konstantin Mikityuk

The reference fuel design currently being considered within the Generation-IV Gas-cooled Fast Reactor (GFR) project is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinders. The fuel is mixed plutonium-uranium carbide, whi ...

Elsevier Science Ltd.2009

Simulation of flow and heat transfer in a differentially heated cubical cavity using coarse Large Eddy Simulation

Konstantin Mikityuk

Two widely used sub-grid scale models namely: the standard and the dynamic Smagorinsky models were tested in a simulation of the flow in a thermally driven 3D cavity at turbulent Rayleigh number Ra = 10(9). The cubical cavity of 0.7 m side-length is set to ...

2023

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

Rakesh Chawla, Konstantin Mikityuk

Several new fuel designs are currently being considered within the generation-IV gas-cooled fast reactor (GFR) project. One of them, which is the GFR reference design, is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinde ...

Elsevier Science Ltd.2007

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

Konstantin Mikityuk

Code verification is an important part of software development process that asserts code correctness. In this work, analytical solutions are used in order to develop a simple multiphysics problem involving coupled fluid dynamics and neutron transport to be ...

2018

Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the Phenix reactor in the frame of end-of-life (EOL) experiments have been used to qualify the FAST code system for Sodium-cooled Fast Reactor (SFR) transient ...

Elsevier2012

Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The end-of-life (EOL) tests recently performed at the Phenix reactor present a unique opportunity to validate computational tools used for Sodium-cooled Fast Reactor (SFR) static and transient analysis. In the first part of the current study, PSI's FAST co ...

Elsevier2012

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

Rakesh Chawla, Konstantin Mikityuk

The Sodium-cooled Fast Reactor (SFR) is one of the most promising Generation IV systems with many advantages, but has one dominating neutronic drawback - a positive sodium void reactivity. The aim of this study is to develop and apply a methodology, which ...

Elsevier2011

A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman

The GeN-Foam multi-physics code enables coupled thermal-hydraulic, neutronic, and thermal-mechanical analysis of fast reactor cores with 3-D unstructured deformable meshes. Advances within the Horizon2020 ESFR-SMART project, as well as trends towards highe ...

ELSEVIER SCIENCE SA2019

FAST code system: Review of recent developments and near-future plans

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The FAST code system is currently being developed and used at the Paul Scherrer Institut for static and transient analysis of the main Generation 4 fast-spectrum reactor concepts: sodium-, helium-, and gas-cooled fast reactors. The code system includes the ...

American Society of Mechanical Engineers2010

FAST: An advanced code system for fast reactor transient analysis

Rakesh Chawla, Konstantin Mikityuk

One of the main goals of the FAST project at PSI is to establish a unique analytical code capability for the core and safety analysis of advanced critical (and sub-critical) fast-spectrum systems for a wide range of different coolants. Both static and tran ...

Elsevier2005

Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic-cooled reactor systems

Rakesh Chawla, Konstantin Mikityuk

A consistent analytical comparison has been made of the transient behavior of critical and subcritical fast-spectrum reactor systems, the basic core design assumed in each case being that of the 80-MW(thermal) mixed-oxide-fueled, Pb-Bi-cooled, experimental ...

American Nucl. Soc.2007

Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The thermal-hydraulic code TRACE is currently being extended at the Paul Scherrer Institute (PSI) for enabling the study of sodium-cooled fast reactor (SFR) core behavior during transients in which boiling is anticipated. An accurate prediction of pressure ...

Elsevier2011

Development of a drift-flux model for heavy liquid metal/gas flow

Rakesh Chawla, Konstantin Mikityuk

The gas lift pump concept based on the bubbling of an inert gas into the primary reactor coolant to enhance natural circulation is currently considered in a number of PbBi-cooled reactor concepts. Thus, the analysis of available void fraction data and the ...

Atomic Energy Society of Japan2005

A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions

Rakesh Chawla, Konstantin Mikityuk

This paper reports a design study for a Brayton cycle machine, which would constitute a dedicated, standalone decay heat removal (DHR) device for the Generation IV Gas-cooled Fast Reactor (GFR). In comparison to the DHR reference strategy developed by the ...

Elsevier2012

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman

The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by de ...

AMER SOC MECHANICAL ENGINEERS2018

Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing - Part I: Methodology demonstration

Konstantin Mikityuk, Vincenzo Anthony Di Nora

This study presents an approach to the selection of optimal energy group structures for multi-group nodal diffusion analyses of Sodium-cooled Fast Reactor cores. The goal is to speed up calculations, particularly in transient calculations, while maintainin ...

2021