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Simulation of Melt Behavior in the Sodium-Cooled Reactor Core Catcher Using the EUCLID/V2 Integrated Computer Code HEFEST-FR Module

Thermal engineering, 2023-11, Vol.70 (11), p.841-848

2023

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Assessment of Parameters of Radioactive Aerosol Release Through Air Duct System Using the SOCRAT/V3 Code

Nuclear technology, 2018-07, Vol.203 (1), p.92-100

2018

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Real-time plasma boundary reconstruction in the KSTAR tokamak using finite element method

Fusion engineering and design, 2007-02, Vol.82 (2), p.163-174

2007

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Verification of an improved module for calculating fission products production in the industry code SOKRAT

Atomic energy (New York, N.Y.), 2013-04, Vol.113 (6), p.435-438

2013

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Integrated plasma physics modelling for the Culham steady state spherical tokamak fusion power plant

Nuclear fusion, 2004-08, Vol.44 (8), p.917-929

2004

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Reconstruction of the North-West Radioactive Track During the Accident at the Fukushima-1 Npp (Japan) Using Sokrat/V3 and Prolog Software

Atomic energy (New York, N.Y.), 2014-07, Vol.116 (3), p.219-224

2014

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Real-Time Calculation of the Accident at the Fukushima-1 NPP (Japan) Using the Sokrat Code

Atomic energy (New York, N.Y.), 2013-07, Vol.114 (3), p.161-168

2013

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Virtual Rogowskii loops for the evaluation of plasma and in-vessel eddy currents in the KSTAR tokamak

Review of scientific instruments, 2006-01, Vol.77 (1)

2006

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Effect of the q(r) profile on electron transport barrier formation in the T-10 tokamak

Plasma physics and controlled fusion, 2003-07, Vol.45 (7), p.1247-1260

2003

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Verification of the BONUS module integrated into the SOCRAT code

Atomic energy (New York, N.Y.), 2009-05, Vol.106 (5), p.316-325

2009

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Virtual Rogowskii loops for the evaluation of plasmaand in-vessel eddy currents in the KSTAR tokamak

Review of scientific instruments, 2006-01, Vol.77 (1), p.016101-016101-3

2006

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Real-time plasma boundary reconstruction in the KSTAR tokamak using finite element method

Fusion engineering and design, 2007, Vol.82 (2), p.163-174

2007

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Analysis of the small-scale plasma perturbations during density limit disruptions in the T-10 tokamak

Nuclear fusion, 2004-07, Vol.44 (7), p.761-771

2004

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Calculation of the energy confinement time and power threshold for L-H transitions in a tokamak with allowance for the parameters of the transport barrier

Plasma physics reports, 2001-01, Vol.27 (1), p.1-17

2001

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Description of turbulent convection in a plasma with the help of interacting Lorentz oscillators

Plasma physics reports, 2000-06, Vol.26 (6), p.465-476

2000

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Non-local plasma response within the canonical profiles transport model

Nuclear fusion, 1998-03, Vol.38 (3), p.373-386

1998

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Toroidal cartography of the high-m magnetic islands in tokamak plasma

Review of Scientific Instruments, 1999-01, Vol.70 (1), p.591-594

1999

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Vertical MHD Stability of the T-15M Tokamak Plasma

Plasma devices and operations, 2003-12, Vol.11 (4), p.219-227

2003

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VERIFICATION OF THE BONUS MODULE INTEGRATED INTO THE SOCRAT CODE

Atomic energy (New York, N.Y.), 2009, Vol.106 (5), p.316-325

2009

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Effect of the q(r) profile on electron transport barrier formation in the T-10 tokamak

Plasma physics and controlled fusion, 2003, Vol.45 (7), p.1247-1260

2003

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Just: Concept development and status

Plasma devices and operations, 1997-07, Vol.5 (2), p.99-126

1997

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Plasma position and current control in T-15 tokamak

Plasma devices and operations, 1992-02, Vol.2 (1), p.61-75

1992

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Efficacy of magnetic diagnostics for plasma boundary reconstruction in KSTAR

Journal of the Korean Physical Society, 2006, 49(III), , pp.79-82

2006

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Testing of the system code designed for simulation of hypothetical beyond design-basis accident on fast breeder reactor

Nuclear energy and technology, 2015-11, Vol.1 (3), p.165-169

2015

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Advancement of modeling deposition and coagulation of aerosols in a nuclear reactor

Nuclear engineering and design, 2009-04, Vol.239 (4), p.641-647

2009

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Simulation of Melt Behavior in the Sodium-Cooled Reactor Core Catcher Using the EUCLID/V2 Integrated Computer Code HEFEST-FR Module

Assessment of Parameters of Radioactive Aerosol Release Through Air Duct System Using the SOCRAT/V3 Code

Real-time plasma boundary reconstruction in the KSTAR tokamak using finite element method

Verification of an improved module for calculating fission products production in the industry code SOKRAT

Integrated plasma physics modelling for the Culham steady state spherical tokamak fusion power plant

Reconstruction of the North-West Radioactive Track During the Accident at the Fukushima-1 Npp (Japan) Using Sokrat/V3 and Prolog Software

Real-Time Calculation of the Accident at the Fukushima-1 NPP (Japan) Using the Sokrat Code

Virtual Rogowskii loops for the evaluation of plasma and in-vessel eddy currents in the KSTAR tokamak

Effect of the q(r) profile on electron transport barrier formation in the T-10 tokamak

Verification of the BONUS module integrated into the SOCRAT code

Virtual Rogowskii loops for the evaluation of plasmaand in-vessel eddy currents in the KSTAR tokamak

Real-time plasma boundary reconstruction in the KSTAR tokamak using finite element method

Analysis of the small-scale plasma perturbations during density limit disruptions in the T-10 tokamak

Calculation of the energy confinement time and power threshold for L-H transitions in a tokamak with allowance for the parameters of the transport barrier

Description of turbulent convection in a plasma with the help of interacting Lorentz oscillators

Non-local plasma response within the canonical profiles transport model

Toroidal cartography of the high-m magnetic islands in tokamak plasma

Vertical MHD Stability of the T-15M Tokamak Plasma

VERIFICATION OF THE BONUS MODULE INTEGRATED INTO THE SOCRAT CODE

Effect of the q(r) profile on electron transport barrier formation in the T-10 tokamak

Just: Concept development and status

Plasma position and current control in T-15 tokamak

Efficacy of magnetic diagnostics for plasma boundary reconstruction in KSTAR

Testing of the system code designed for simulation of hypothetical beyond design-basis accident on fast breeder reactor

Advancement of modeling deposition and coagulation of aerosols in a nuclear reactor

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