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First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor

Annals of nuclear energy, 2009-04, Vol.36 (3), p.337-343

2009

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Simulation of molten metal freezing behavior on to a structure

Nuclear engineering and design, 2008-10, Vol.238 (10), p.2706-2717

2008

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Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-Pin Bundle Experiment

Journal of nuclear science and technology, 2009-08, Vol.46 (8), p.799-808

2009

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Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors

Nuclear engineering and design, 2018-01, Vol.326, p.392-402

2018

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Simulation of central sloshing experiments with smoothed particle hydrodynamics (SPH) method

Nuclear engineering and design, 2011-08, Vol.241 (8), p.3086-3096

2011

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Numerical investigation of SIMMER code for fuel-coolant interaction

International journal of hydrogen energy, 2016-05, Vol.41 (17), p.7227-7232

2016

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Preliminary Evaluation of Recriticality Potential for ESFR Core and Conditions for Its Elimination

Nuclear technology, 2015-09, Vol.191 (3), p.246-253

2015

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Probabilistic evaluation of the energetics upper bound during the transition phase of an unprotected loss of flow accident for a sodium cooled fast reactor by using a Phenomenological Relationship Diagram

Nuclear engineering and design, 2019-01, Vol.341, p.146-154

2019

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ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides

Energy procedia, 2015-05, Vol.71, p.130-139

2015

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Fundamental solution of nuclear solitary wave

Energy conversion and management, 2012-07, Vol.59, p.40-49

2012

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Theoretical and numerical studies of TWR based on ESFR core design

Energy conversion and management, 2013-08, Vol.72, p.12-18

2013

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Neutron transport model based on the transmission probability method

Energy conversion and management, 2013-08, Vol.72, p.33-38

2013

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Probabilistic Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium-Cooled SMR by using a Phenomenological Relationship Diagram

Energy procedia, 2017-01, Vol.131, p.222-229

2017

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Study on Severe Accident Scenarios: Pin Failure Possibility of MYRRHA-FASTEF Critical Core

Energy procedia, 2015-05, Vol.71, p.14-21

2015

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Molten salt related extensions of the SIMMER-III code and its application for a burner reactor

Nuclear engineering and design, 2006-08, Vol.236 (14), p.1580-1588

2006

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Transient analyses of the 400MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III

Nuclear engineering and design, 2010-10, Vol.240 (10), p.3481-3494

2010

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Neutron transport model based on the transmission probability method: The III. International Conference on Nuclear and Renewable Energy Ressources NURER2012

Energy conversion and management, 2013, Vol.72, p.33-38

2013

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Theoretical and numerical studies of TWR based on ESFR core design: The III. International Conference on Nuclear and Renewable Energy Ressources NURER2012

Energy conversion and management, 2013, Vol.72, p.12-18

2013

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Plutonium and Minor Actinides incineration options using innovative Na-cooled fast reactors: Impacting on phasing-out and on-going fuel cycles

Progress in nuclear energy (New series), 2015-07, Vol.82, p.58-63

2015

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Heterogeneous cores for improved safety performance A case study : The supercritical water fast reactor

Nuclear engineering and design, 2006-08, Vol.236 (14-16), p.1573-1579

2006

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Preliminary Safety Analysis of Mixed Oxide Sphere-pac Driver Fuels in the CP-ESFR WH Core

Energy procedia, 2015, Vol.71, p.149-158

2015

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Fundamental burn-up mode in a pebble-bed type reactor

Progress in nuclear energy (New series), 2008-03, Vol.50 (2), p.219-224

2008

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Numerical studies of nuclear traveling waves in a supercritical water cooled fast reactor

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.806-813

2011

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Development of a plate-type fuel model for the neutronics and thermal-hydraulics coupled code – SIMMER-III – and its application to the analyses of SPERT

Nuclear engineering and design, 2010-10, Vol.240 (10), p.3495-3503

2010

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Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code

Nuclear engineering and design, 2005-12, Vol.235 (24), p.2594-2611

2005

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First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor

Simulation of molten metal freezing behavior on to a structure

Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-Pin Bundle Experiment

Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors

Simulation of central sloshing experiments with smoothed particle hydrodynamics (SPH) method

Numerical investigation of SIMMER code for fuel-coolant interaction

Preliminary Evaluation of Recriticality Potential for ESFR Core and Conditions for Its Elimination

Probabilistic evaluation of the energetics upper bound during the transition phase of an unprotected loss of flow accident for a sodium cooled fast reactor by using a Phenomenological Relationship Diagram

ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides

Fundamental solution of nuclear solitary wave

Theoretical and numerical studies of TWR based on ESFR core design

Neutron transport model based on the transmission probability method

Probabilistic Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium-Cooled SMR by using a Phenomenological Relationship Diagram

Study on Severe Accident Scenarios: Pin Failure Possibility of MYRRHA-FASTEF Critical Core

Molten salt related extensions of the SIMMER-III code and its application for a burner reactor

Transient analyses of the 400MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III

Neutron transport model based on the transmission probability method: The III. International Conference on Nuclear and Renewable Energy Ressources NURER2012

Theoretical and numerical studies of TWR based on ESFR core design: The III. International Conference on Nuclear and Renewable Energy Ressources NURER2012

Plutonium and Minor Actinides incineration options using innovative Na-cooled fast reactors: Impacting on phasing-out and on-going fuel cycles

Heterogeneous cores for improved safety performance A case study : The supercritical water fast reactor

Preliminary Safety Analysis of Mixed Oxide Sphere-pac Driver Fuels in the CP-ESFR WH Core

Fundamental burn-up mode in a pebble-bed type reactor

Numerical studies of nuclear traveling waves in a supercritical water cooled fast reactor

Development of a plate-type fuel model for the neutronics and thermal-hydraulics coupled code – SIMMER-III – and its application to the analyses of SPERT

Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code

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