International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium cooled fast reactors. The ASTRID project is a demonstrator of such technology exhibiting innovative features such as the CFV core which has a negative sodium void reactivity effect. In order to study in details the uncertainty associated to this parameter, we split it into two components : the central component (CC) which is a positive reactivity effect due to spectrum changes and the leakage component (LC) which is a negative reactivity effect due to the increase of the neutron mean free path. This paper presents the development of an innovative GPT procedure for computing sensitivities of the CC and the LC. With such sensitivities and the us...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...
A renewed assessment of the sodium void reactivity worth is being presented in this paper after new ...
International audienceFor the next generation fast reactor design, theGeneration IV International Fo...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
The EU 7th Framework Project ESNII+ was launched in 2013 in support of the initiative ESNII (Europea...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
Engineering of innovative reactor concepts requires computational tools capable of producing results...
International audienceEvaluating uncertainties on reactivity is a major issue for conception of nucl...
International audienceThe characteristics of any nuclear power plant should be determined according ...
Special Issue on 4th International Workshop on Nuclear Data Covariances, October 2–6, 2017, Aix en P...
Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to r...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
Fast Spectrum Nuclear Reactors are a long term solution for energy production, as they can be used t...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...
A renewed assessment of the sodium void reactivity worth is being presented in this paper after new ...
International audienceFor the next generation fast reactor design, theGeneration IV International Fo...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
The EU 7th Framework Project ESNII+ was launched in 2013 in support of the initiative ESNII (Europea...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
Engineering of innovative reactor concepts requires computational tools capable of producing results...
International audienceEvaluating uncertainties on reactivity is a major issue for conception of nucl...
International audienceThe characteristics of any nuclear power plant should be determined according ...
Special Issue on 4th International Workshop on Nuclear Data Covariances, October 2–6, 2017, Aix en P...
Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to r...
International audienceThe present work details a further investigation of the SNEAK-12A experimental...
Fast Spectrum Nuclear Reactors are a long term solution for energy production, as they can be used t...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceA benchmark analysis was launched within the Work Package on Core Safety of th...
A renewed assessment of the sodium void reactivity worth is being presented in this paper after new ...
International audienceFor the next generation fast reactor design, theGeneration IV International Fo...