A concept of fluid dynamic code for molten salt reactor analysis with Open FOAM (in session "Poster Session")
A FRAMEWORK FOR MULTI-PHYSICS MODELING, DESIGN OPTIMIZATION AND UNCERTAINTY QUANTIFICATION OF FAST SPECTRUM LIQUID FUEL MOLTEN SALT REACTORS (in session "Technical Session 1-1: Advanced application of open-source tools to nuclear engineering problems")
Active coding assignments in nuclear reactor modelling (in session "Poster Session")
AN OPEN-SOURCE DATA-CENTRIC REPRESENTATION OF THE FAST FLUX TEST FACILITY ISOTHERMAL BENCHMARK CORE (in session "Poster Session")
Challenges and Lessons Learned from 10 Years of OpenMC Development (in session "General Session 1-3: Motivations, experience, and challenges for the open-source approach")
CONTRIBUTING TO OPENFOAM FOUNDATION RELEASE - AN EFFECTIVE CODE DEVELOPMENT STRATEGY (in session "General Session 1-1: Motivations, experience, and challenges for the open-source approach")
Development and maintenance of OpenFOAM_RCS for German nuclear safety research related to the reactor cooling system (in session "Poster Session")
DEVELOPMENT OF ACCESSIBLE CODES FOR NUCLEAR SAFETY ANALYSIS IN THAILAND (in session "Poster Session")
Development of an open source tool for water hammer and fluid-structure interaction simulation in nuclear reactor systems (in session "Poster Session")
Development of Post Processor for VSOP'94 Output (in session "Poster Session")
DEVELOPMENT OF THE OPEN-SOURCE MULTI-DIMENSIONAL FUEL PERFORMANCE CODE OFFBEAT (in session "Technical Session 2-1: Recent developments in open-source tools")
DRAGON and DONJON: a legacy open-source reactor physics project at Polytechnique Montréal (in session "General Session 1-2: Motivations, experience, and challenges for the open-source approach")
Enabling techniques within OpenMC for dynamic models of molten salt reactors (in session "Poster Session")
FLAMEFOAM: AN OPENFOAM BASED SOLVER FOR PRACTICAL TURBULENT PREMIXED COMBUSTION SIMULATION (in session "Technical Session 1-1: Advanced application of open-source tools to nuclear engineering problems")
FOUNDATIONS FOR A FISSION BATTERY DIGITAL TWIN (in session "Poster Session")
High performence calculation enhancement using massive parallelization with TRUST and TrioCFD (in session "Technical Session 2-1: Recent developments in open-source tools")
Investigating efficient coupling of Finite Element Analysis with Machine Learning to optimise a laboratory experiment. (in session "Poster Session")
MFEM-MGIS-MFRONT, a HPC mini-application targeting nonlinear thermo-mechanical simulations of nuclear fuels at mesoscale (in session "Technical Session 1-2: Advanced application of open-source tools to nuclear engineering problems")
MFront: an open-source code generation tool for the rigorous management of material knowledge in the PLEIADES and MAP platforms (in session "Poster Session")
MODIFICATION OF OPEN SOURCE MONTE CARLO CODE OPENMC TO INCLUDE TIME-DEPENDENCE IN A FISSILE SYSTEM INCLUDING INDIVIDUAL DELAYED NEUTRON PRECURSORS (in session "Poster Session")
MULTI-SCALE COMPUTATIONAL ANALYSIS TO PREDICT THE IRRADIATION-INDUCED CHANGE IN ENGINEERING PROPERTIES OF FUSION REACTOR MATERIALS. (in session "Poster Session")
On Application of Open-Source Learning Models to Nuclear Engineering (in session "General Session 1-2: Motivations, experience, and challenges for the open-source approach")
ONIX: AN OPEN-SOURCE DEPLETION CODE FOR REACTOR ANALYSIS AND NUCLEAR SECURITY (in session "Technical Session 2-2: Recent developments in open-source tools")
Open source neutron noise modelling (in session "Poster Session")
Open source tools in support of multiphysics simulation for fusion (in session "Poster Session")
OPEN-SOURCING SAFETY, RISK, AND RELIABILITY TOOLS (in session "Technical Session 1-2: Advanced application of open-source tools to nuclear engineering problems")
RETROSPECT, STATUS AND PERSPECTIVE OF THE DEVELOPMENT OF ‘CONTAINMENTFOAM’ (in session "Technical Session 2-2: Recent developments in open-source tools")
Scalable Tightly-Coupled Multi-physics for Fusion Reactors with AURORA (in session "Technical Session 2-2: Recent developments in open-source tools")
SCIANTIX OPEN-SOURCE CODE FOR FISSION GAS BEHAVIOUR: OBJECTIVES AND FORESEEN DEVELOPMENTS (in session "Technical Session 2-1: Recent developments in open-source tools")
SCONE: AN OPEN-SOURCE MONTE CARLO NEUTRON TRANSPORT CODE FOR RESEARCH AND TEACHING (in session "General Session 1-3: Motivations, experience, and challenges for the open-source approach")
THE GEN-FOAM MULTI-PHYSICS SOLVER AS A COLLABORATIVE EFFORT TOWARDS AN OPEN-SOURCE PLATFORM FOR REACTOR ANALYS: A HISTORICAL PERSPECTIVE AND LESSONS LEANRT (in session "General Session 1-1: Motivations, experience, and challenges for the open-source approach")
THE GEN-FOAM MULTI-PHYSICS SOLVER FOR REACTOR ANALYISIS: STATUS AND ONGOING DEVELOPMENTS (in session "Poster Session")
The Modern Nuclear Energy Agency Data Bank: An Integrated Hub for Code and Data Development and Validation (in session "General Session 1-2: Motivations, experience, and challenges for the open-source approach")
Updates On Open-Source Multiphysics Endeavors with OpenMC (in session "Technical Session 2-1: Recent developments in open-source tools")
USE OF OPEN-SOURCE MODELICA-BASED LIBRARIES AS SYSTEM CODE FOR NUCLEAR POWER PLANT SIMULATION (in session "Technical Session 1-1: Advanced application of open-source tools to nuclear engineering problems")
USE OF OPEN-SOURCE SOFTWARE AT ENEA FOR NUCLEAR REACTOR SAFETY SIMULATIONS (in session "General Session 1-3: Motivations, experience, and challenges for the open-source approach")
USE OF OPEN-SOURCE TOOLS IN EDUCATION AND TRAINING: EXPERIENCE FROM POLIMI AND EPFL (in session "General Session 1-2: Motivations, experience, and challenges for the open-source approach")
Validation of an OpenFOAM gas distribution solver for containment analysis (in session "Poster Session")
VANGARD: A GPU-BASED HIGH-SPEED PINWISE NODAL CORE ANALYSIS CODE (in session "Poster Session")
Verification & Validation process in the open-source TRUST/TrioCFD Platform (in session "Poster Session")
VERIFICATION OF MULTIPHYSICS COUPLING TECHNIQUES FOR MODELING OF MOLTEN SALT REACTORS (in session "Poster Session")
“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” (in session "Poster Session")
Include materials from selected contributions
