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13:30
MULTI-SCALE COMPUTATIONAL ANALYSIS TO PREDICT THE IRRADIATION-INDUCED CHANGE IN ENGINEERING PROPERTIES OF FUSION REACTOR MATERIALS.
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Salahudeen Mohamed Kunju
(Swansea University/UKAEA)
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13:30
Verification & Validation process in the open-source TRUST/TrioCFD Platform
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Julie Darona
(CEA)
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13:30
Investigating efficient coupling of Finite Element Analysis with Machine Learning to optimise a laboratory experiment.
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Rhydian Lewis
(Swansea University)
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13:30
VERIFICATION OF MULTIPHYSICS COUPLING TECHNIQUES FOR MODELING OF MOLTEN SALT REACTORS
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Jacob Groth-Jensen
(seaborg technologies)
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13:30
Open source tools in support of multiphysics simulation for fusion
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Andrew Davis
(United Kingdom Atomic Energy Authority)
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13:50
Validation of an OpenFOAM gas distribution solver for containment analysis
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Jörn Stewering
(Gesellschaft für Anlagen- und Reaktorsicherheit)
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13:50
Active coding assignments in nuclear reactor modelling
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Christophe Demazière
(Chalmers University of Technology)
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13:50
Open source neutron noise modelling
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Christophe Demazière
(Chalmers University of Technology)
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13:50
THE GEN-FOAM MULTI-PHYSICS SOLVER FOR REACTOR ANALYISIS: STATUS AND ONGOING DEVELOPMENTS
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carlo Fiorina
(EPFL, Switzerland)
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13:50
Development and maintenance of OpenFOAM_RCS for German nuclear safety research related to the reactor cooling system
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Ronald Lehnigk
(Helmholtz-Zentrum Dresden - Rossendorf)
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14:15
MODIFICATION OF OPEN SOURCE MONTE CARLO CODE OPENMC TO INCLUDE TIME-DEPENDENCE IN A FISSILE SYSTEM INCLUDING INDIVIDUAL DELAYED NEUTRON PRECURSORS
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Jaime Romero-Barrientos
(CCHEN)
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14:15
FOUNDATIONS FOR A FISSION BATTERY DIGITAL TWIN
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Jeren Browning
(Idaho National Laboratory)
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14:15
VANGARD: A GPU-BASED HIGH-SPEED PINWISE NODAL CORE ANALYSIS CODE
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SEOYOON JEON
(Seoul National University)
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14:15
“DEVELOPMENT OF CODES FOR CALCULATING THE CORROSION OF STEEL CLADDING OF FUEL ELEMENTS WITH MIXED NITRIDE FUEL, TAKING INTO ACCOUNT THE SEGREGATION OF IMPURITIES AT GRAIN BOUNDARIES”
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ALEXANDER IVANOV
(NRC "Kurchatov Institute")
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14:40
Development of an open source tool for water hammer and fluid-structure interaction simulation in nuclear reactor systems
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Marcelo Rocha
(IPEN/CNEN)
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14:40
Enabling techniques within OpenMC for dynamic models of molten salt reactors
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Erik Knudsen
(Copenhagen Atomics)
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14:40
DEVELOPMENT OF ACCESSIBLE CODES FOR NUCLEAR SAFETY ANALYSIS IN THAILAND
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Wasin Vechgama
(Nuclear Technology Research and Development Center, Thailand Institute of Nuclear Technology (Public Organization), Bangkok, Thailand)
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14:40
Development of Post Processor for VSOP'94 Output
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Anik Purwaningsih
(National Nuclear Energy Agency of Indonesia)
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14:40
MFront: an open-source code generation tool for the rigorous management of material knowledge in the PLEIADES and MAP platforms
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Thomas Helfer
(CEA)
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14:40
AN OPEN-SOURCE DATA-CENTRIC REPRESENTATION OF THE FAST FLUX TEST FACILITY ISOTHERMAL BENCHMARK CORE
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Nicholas Touran
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14:40
A concept of fluid dynamic code for molten salt reactor analysis with Open FOAM
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Azizul Khakim
(BAPETEN (Nuclear Energy Regulatory Agency))
