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Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Annals of nuclear energy, 2015-01, Vol.75, p.249-260

2015

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Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modeling

Nuclear engineering and design, 2010-09, Vol.240 (9), p.2271-2280

2010

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Experiments at the mixing test facility ROCOM for benchmarking of CFD codes

Nuclear engineering and design, 2008-03, Vol.238 (3), p.566-576

2008

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Calculation of the VVER-1000 coolant transient benchmark using the coupled code systems DYN3D/RELAP5 and DYN3D/ATHLET

Nuclear engineering and design, 2007-09, Vol.237 (15), p.1938-1951

2007

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Experimental determination of the boron concentration distribution in the primary circuit of a PWR after a postulated cold leg small break loss-of-coolant-accident with cold leg safety injection

Nuclear engineering and design, 2008-07, Vol.238 (7), p.1788-1801

2008

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Child-onset systemic lupus erythematosus is associated with a higher incidence of myopericardial manifestations compared to adult-onset disease

Lupus, 2018-11, Vol.27 (13), p.2146-2154

2018

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On the use of different analytical solutions for recalculation of the YALINA-Booster experiment SC3A

Progress in nuclear energy (New series), 2012-07, Vol.58, p.11-20

2012

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A two group analytical approximation solution for an external source problem without separation of space and time

Annals of nuclear energy, 2010-07, Vol.37 (7), p.942-952

2010

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Influence of the Pipe Diameter on the Structure of the Gas-Liquid Interface in a Vertical Two-Phase Pipe Flow

Nuclear technology, 2005-10, Vol.152 (1), p.3-22

2005

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Core response of a PWR to a slug of under-borated water

Nuclear engineering and design, 2004-05, Vol.230 (1), p.121-132

2004

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Hydrodynamic phenomena in the downcomer during flow rate transients in the primary circuit of a PWR

Nuclear engineering and design, 2007-04, Vol.237 (7), p.732-748

2007

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A photo-neutron source for time-of-flight measurements at the radiation source ELBE

Annals of nuclear energy, 2007, Vol.34 (1), p.36-50

2007

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ATWS analysis for PWR using the coupled code system DYN3D/ATHLET

Annals of nuclear energy, 2009-08, Vol.36 (8), p.1230-1234

2009

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Use of echocardiography at diagnosis and detection of acute cardiac disease in youth with systemic lupus erythematosus

Lupus, 2018-07, Vol.27 (8), p.1348-1357

2018

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State of the art of controlling loss-of-coolant accidents with release of insulation material

Kerntechnik (1987), 2011-03, Vol.76 (1), p.7-7

2011

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TOPFLOW – a new multipurpose thermalhydraulic test facility for the investigation of steady state and transient two phase flow phenomena

Kerntechnik (1987), 2022-03, Vol.66 (4), p.209-213

2022

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The nELBE Neutron Time of Flight Facility

Journal of the Korean Physical Society, 2011, 59(23), , pp.1593-1596

2011

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Validation of coupled codes using VVER plant measurements

Nuclear engineering and design, 2005-02, Vol.235 (2), p.507-519

2005

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Coupled thermal structural analysis of LWR vessel creep failure experiments

Nuclear engineering and design, 2001-09, Vol.208 (3), p.265-282

2001

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The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

Kerntechnik (1987), 2006-08, Vol.71 (4), p.163-173

2006

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Verification and Validation of Numerical Models of the Transport of Insulation Debris

The journal of computational multiphase flows (Online), 2012-09, Vol.4 (3), p.255-270

2012

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Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments

Annals of nuclear energy, 2006, Vol.33 (2), p.126-148

2006

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Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

Annals of nuclear energy, 2003-07, Vol.30 (10), p.1033-1063

2003

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Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility

Nuclear engineering and design, 2005-02, Vol.235 (2), p.485-506

2005

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A Three-Scale Expansion Solution for a Time-Dependent P 1 Neutron Transport Problem with External Source

Nuclear science and engineering, 2009-10, Vol.163 (2), p.152-174

2009

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Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

Experiments on slug mixing under natural circulation conditions at the ROCOM test facility using high-resolution measurement techniques and numerical modeling

Experiments at the mixing test facility ROCOM for benchmarking of CFD codes

Calculation of the VVER-1000 coolant transient benchmark using the coupled code systems DYN3D/RELAP5 and DYN3D/ATHLET

Experimental determination of the boron concentration distribution in the primary circuit of a PWR after a postulated cold leg small break loss-of-coolant-accident with cold leg safety injection

Child-onset systemic lupus erythematosus is associated with a higher incidence of myopericardial manifestations compared to adult-onset disease

On the use of different analytical solutions for recalculation of the YALINA-Booster experiment SC3A

A two group analytical approximation solution for an external source problem without separation of space and time

Influence of the Pipe Diameter on the Structure of the Gas-Liquid Interface in a Vertical Two-Phase Pipe Flow

Core response of a PWR to a slug of under-borated water

Hydrodynamic phenomena in the downcomer during flow rate transients in the primary circuit of a PWR

A photo-neutron source for time-of-flight measurements at the radiation source ELBE

ATWS analysis for PWR using the coupled code system DYN3D/ATHLET

Use of echocardiography at diagnosis and detection of acute cardiac disease in youth with systemic lupus erythematosus

State of the art of controlling loss-of-coolant accidents with release of insulation material

TOPFLOW – a new multipurpose thermalhydraulic test facility for the investigation of steady state and transient two phase flow phenomena

The nELBE Neutron Time of Flight Facility

Validation of coupled codes using VVER plant measurements

Coupled thermal structural analysis of LWR vessel creep failure experiments

The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

Verification and Validation of Numerical Models of the Transport of Insulation Debris

Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments

Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility

A Three-Scale Expansion Solution for a Time-Dependent P 1 Neutron Transport Problem with External Source

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