International audienceA fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA within the PLEIADES simulation framework. The present main goal of GERMINAL is to meet the needs of the design studies of ASTRID, the future Advanced Sodium Technological Reactor for Industrial Demonstration in France. Recent works have been conducted to improve the modelling of different physical mechanisms having a strong influence on the design criteria evaluation. Thus, the formulation of the fuel pellet fragments relocation model has been revisited, by introducing a dependence to the thermal gradient inside the pellet. The description of this mechanism represents a key point to evaluate the pellet-to-cladding gap closure and the margin ...
This deliverable addresses one of the benchmark activities foreseen in Task 7.3 of INSPYRE, which fo...
International audienceFuture sodium cooled fast reactors (SFRs) with Minor Actinide (MA) burning pot...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
International audienceA fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA...
International audienceA fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA...
International audienceGERMINAL is a fuel performance code developed by the French Commission of Alte...
International audienceWithin the PLEIADES simulation platform co-developed by CEA, EDF and FRAMATOME...
International audienceIn the framework of the basic design of ASTRID (Advanced Sodium Technological ...
International audienceThe reference fuel design for french Sodium nuclear Fast Reactor (SFR) consist...
The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for ...
Many scenario studies conducted by several countries consider the progressive deployment of low void...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
International audienceIn this work, two different thermodynamic softwares, ANGE using the TBASE data...
International audienceDuring the years 2018 and 2019 of the ASTRID program, a simulation program on ...
This deliverable addresses one of the benchmark activities foreseen in Task 7.3 of INSPYRE, which fo...
International audienceFuture sodium cooled fast reactors (SFRs) with Minor Actinide (MA) burning pot...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...
International audienceA fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA...
International audienceA fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA...
International audienceGERMINAL is a fuel performance code developed by the French Commission of Alte...
International audienceWithin the PLEIADES simulation platform co-developed by CEA, EDF and FRAMATOME...
International audienceIn the framework of the basic design of ASTRID (Advanced Sodium Technological ...
International audienceThe reference fuel design for french Sodium nuclear Fast Reactor (SFR) consist...
The design phase and safety assessment of Generation IV liquid metal-cooled fast reactors calls for ...
Many scenario studies conducted by several countries consider the progressive deployment of low void...
Nuclear fuel undergoes various changes in its properties and composition as it is irradiated in a nu...
International audienceIn this work, two different thermodynamic softwares, ANGE using the TBASE data...
International audienceDuring the years 2018 and 2019 of the ASTRID program, a simulation program on ...
This deliverable addresses one of the benchmark activities foreseen in Task 7.3 of INSPYRE, which fo...
International audienceFuture sodium cooled fast reactors (SFRs) with Minor Actinide (MA) burning pot...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 20...