A renewed assessment of the sodium void reactivity worth is being presented in this paper after new cross-section evaluations (JEFZ)l and computational methods (ECCO/ERANOS)2,3 have been established. The CIRAN04 experimental programme, which provides the experimental data base for Plutonium Burning cores5 (CAPRA design) is also a reason for such a renewed study. A detailed analysis of the experiments requires the use of transport theory with an accurate representation of anisotropic streaming and the use of perturbation theory for transport methods. This allows the separation of the global effect into a leakage term and a non-leakage term and the application of known method corrections (the anisotropy of streaming not yet implemented) to th...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
The use of zirconium hydride (Th–ZrH1.6) blankets in a thorium-fuelled sodium-cooled reactor for voi...
AbstractThis study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
Abstract: The results of calculations of sodium-void reactivity effect, measured on the 'Z...
International audienceThe characteristics of any nuclear power plant should be determined according ...
International audienceAs part of a bilateral agreement on the study of large axially-heterogeneous o...
International audienceMinor actinides transmutation is a solution to decrease the long-term radiotox...
An analysis of metal-, oxide, and nitride-fueled advanced liquid metal reactor cores was performed t...
The core-wide* void coefficient of reactivity has been determined both theoretically and experimenta...
paper 9205International audienceThe future of nuclear energy may require breeding and optimized wast...
This paper has presented the results of a computational benchmark and independent calculations to ve...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
The Molten Salt Fast Reactor is a fast-spectrum molten salt reactor under development in the framewo...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
The use of zirconium hydride (Th–ZrH1.6) blankets in a thorium-fuelled sodium-cooled reactor for voi...
AbstractThis study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
International audienceFor ensuring sustainable nuclear energy, France has chosen to develop sodium c...
Abstract: The results of calculations of sodium-void reactivity effect, measured on the 'Z...
International audienceThe characteristics of any nuclear power plant should be determined according ...
International audienceAs part of a bilateral agreement on the study of large axially-heterogeneous o...
International audienceMinor actinides transmutation is a solution to decrease the long-term radiotox...
An analysis of metal-, oxide, and nitride-fueled advanced liquid metal reactor cores was performed t...
The core-wide* void coefficient of reactivity has been determined both theoretically and experimenta...
paper 9205International audienceThe future of nuclear energy may require breeding and optimized wast...
This paper has presented the results of a computational benchmark and independent calculations to ve...
International audienceCEA is largely involved in the study of GEN-IV Sodium Fast Reactors (SFR). Som...
The Molten Salt Fast Reactor is a fast-spectrum molten salt reactor under development in the framewo...
The EU 7th Framework ESNII+ project was launched in 2013 with the strategic orientation of preparing...
The use of zirconium hydride (Th–ZrH1.6) blankets in a thorium-fuelled sodium-cooled reactor for voi...
AbstractThis study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6...