International audienceA good knowledge of the decay heat of the various elements of the core (fissile and fertile zones, structures, sodium,..) as well as the associated uncertainties is critical for the operation of a nuclear facility, but also at the design stage as in the case of the ASTRID technological demonstrator. For this reactor, the amount of decay heat is all the more important as it will strongly impact the design of the dedicated EPur system. The uncertainties on the decay heat calculation of a sodium fast reactor that are currently used at CEA were defined several decades ago and are very high, especially at short cooling times. They may thus be penalizing for the design and operation of ASTRID. These past uncertainty assessm...
In the present paper, firstly, we review our previous works on uncertainty quantification (UQ) of re...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceThe decay heat is a crucial issue for in-core safety after reactor shutdown an...
International audienceDecay heat is a crucial issue for in-core safety after reactor shutdown and th...
International audienceThe DARWIN3-SFR tool is the new calculation tool dedicated to the estimation o...
International audienceThe DARWIN2.3 package is dedicated to spent fuel characterization in general a...
This PhD study is in the field of nuclear energy, the back end of nuclear fuel cycle and uncertainty...
The accurate prediction of the decay heat is essential, especially for nuclear power plant safety pu...
The knowledge of the decay heat quantity and the associated uncertainties are important issues for t...
Decay heat is the thermal power released by radioactive decays of unstable isotopes after the nuclea...
The EU 7th Framework Project ESNII+ was launched in 2013 in support of the initiative ESNII (Europea...
Ce travail de thèse s’inscrit dans le domaine de l’énergie nucléaire, de l’aval du cycle du combusti...
In the present paper, firstly, we review our previous works on uncertainty quantification (UQ) of re...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceA good knowledge of the decay heat of the various elements of the core (fissil...
International audienceThe decay heat is a crucial issue for in-core safety after reactor shutdown an...
International audienceDecay heat is a crucial issue for in-core safety after reactor shutdown and th...
International audienceThe DARWIN3-SFR tool is the new calculation tool dedicated to the estimation o...
International audienceThe DARWIN2.3 package is dedicated to spent fuel characterization in general a...
This PhD study is in the field of nuclear energy, the back end of nuclear fuel cycle and uncertainty...
The accurate prediction of the decay heat is essential, especially for nuclear power plant safety pu...
The knowledge of the decay heat quantity and the associated uncertainties are important issues for t...
Decay heat is the thermal power released by radioactive decays of unstable isotopes after the nuclea...
The EU 7th Framework Project ESNII+ was launched in 2013 in support of the initiative ESNII (Europea...
Ce travail de thèse s’inscrit dans le domaine de l’énergie nucléaire, de l’aval du cycle du combusti...
In the present paper, firstly, we review our previous works on uncertainty quantification (UQ) of re...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and mea...