A5014667545- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Graphite, nuclear technology, radiation studies
- Combustion and Detonation Processes
- Heat transfer and supercritical fluids
- Subcritical and Supercritical Water Processes
- Nuclear Physics and Applications
- Particle Dynamics in Fluid Flows
- Radioactivity and Radon Measurements
- Radioactive contamination and transfer
- Meteorological Phenomena and Simulations
- Metallurgical Processes and Thermodynamics
- Atmospheric and Environmental Gas Dynamics
- Spacecraft Design and Technology
- Heat Transfer and Optimization
- Spacecraft and Cryogenic Technologies
- Risk and Safety Analysis
- 3D Surveying and Cultural Heritage
- Radiation Detection and Scintillator Technologies
- Logistics and Infrastructure Analysis
- Geophysics and Gravity Measurements
- Fatigue and fracture mechanics
European Commission
2015-2024
Joint Research Center
2023-2024
Joint Research Centre
2011-2021
Energy Research Centre of the Netherlands
2011
Imperial College London
2002
During a hypothetical severe accident in nuclear reactor most of the radioactivity would be released from damaged core and broken primary circuit form aerosols chemical vapours gases. However effective radio-toxicity per unit release fuel depends both on mass as well. The fission products transport has been analysed for Medium Break cold leg Loss Of Coolant Accident (MBLOCA) combined with total loss electric power supply (Station Black Out) reference PWR 1000 using integral code ASTECV1.3...
This paper presents simulation results of the CABRI BI1 test using code ASTEC-Na, currently under development, as well a comparison with available experimental data. The EU-JASMIN project (7th FP EURATOM) centres on development and validation new severe accident analysis ASTEC-Na (Accident Source Term Evaluation Code) for sodium-cooled fast reactors whose owner developer is IRSN. A series experiments performed in past (CABRI/SCARABEE experiments) to be conducted sodium facility KASOLA have...
The EU-JASMIN project (7th FP of EURATOM) has been centred on the development and validation new severe accident analysis code ASTEC-Na (Accident Source Term Evaluation Code) for Sodium-cooled Fast Reactors (SFR). such computational tool being able to assist safety innovative reactor concepts is crucial importance. One challenging issues when modelling SFRs neutronic reactivity feedbacks. This paper presents model implemented in representing effects SFR as well benchmarking results a ULOF...
The demonstrated technological feasibility of Sodium-cooled Fast Reactors (SFRs) makes them stand out among the other reactor concepts proposed by Generation IV International Forum (GIF) for short-term deployment. availability reliable computational tools in support safety analyses and plant simulations under complex transient scenarios is essential to assure SFR's compliance with highest goals. Answering this need, a multi-physics three-dimensional core system model being developed enable...
With the aim to develop a joint proposal for harmonised European methodology safety assessment of advanced reactors with fast neutron spectrum, SARGEN_IV (Safety Assessment Reactors Gen IV) Euratom coordination action project gathered together twenty-two partners' experts from twelve EU Member States. The group consisted eight Technical Safety Organisations involved in Organisation Network (ETSON), Commission's Joint Research Centre (JRC), system designers, industrial vendors as well...
Abstract The computational codes used in the evaluation of European sodium fast reactor—safety measures assessment and research tools(ESFR-SMART) reactor performance specifically their boiling models are assessed using two KNS-37 loss flow (LOF) experiments, i.e., L22 L29 tests, where onset two-phase regime up to dry-out occurred. well-equipped experimental facility provided very valuable information for understanding physical phenomena occurring a 37-pin subassembly under LOF conditions, as...
<ns4:p>Decarbonization of energy production is key in today’s societies and nuclear holds an essential place this prospect. Besides heavy-duty electricity production, other industrial communal needs could be served by integrating novel systems, among which are low-power devices, like small modular reactors (SMRs). The ELSMOR (towards European Licensing Small Modular Reactors) project addresses topic as answer to the Horizon 2020 Euratom NFRP-2018-3 call. consortium includes 15 partners from...