An analysis of the influence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed. A special emphasis was given to the total control rods worth in order to describe qualitatively and quantitatively its change with MA content. All computations were performed with a homogeneous assembly model of modified BN-600 sodium-cooled fast reactor core with 0, 3 and 6% of MA. A model was prepared for the Monte Carlo neutron transport code MCNP5 for fresh fuel in the beginning-of-life (BOL) state. Additionally, some other parameters, such as Doppler constant, sodium void reactivity, delayed neutron fraction, neutron fluxes and neutron spectra distribution, were computed and their change ...
In sodium fast reactor designs, the fuel related inherent negative reactivity feedback is accomplish...
A comparative evaluation of minor actinide (MA) transmutation property was performed for various fas...
This paper describes the neutron transport calculations for the sodium-cooled fast reactors by using...
International audienceThe reduction of the initial excess reactivity in fast reactor cores would enh...
International audienceMinor actinides transmutation is a solution to decrease the long-term radiotox...
According to the Generation IV International Forum Technology Roadmap, Sodium Fast Reactors (SFR) co...
International audienceThe small modular sodium-cooled fast reactor (SMSFR) is an important component...
This research developed a design of an innovative sodium-cooled fast reactor (SFR) for minor actinid...
This paper shows that lead-cooled and sodium-cooled fast reactors (LFRs and SFRs) can preferentially...
Neutron transport and depletion calculations are performed in combination with various nuclear data ...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
In this paper, neutronics and severe safety characteristics of Lead-cooled Fast Reactor (LFR) and So...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
The sensitivity of two operational output parameters, criticality and isotopic composition during bu...
This paper presents a new design for a small modular sodium-cooled fast reactor core with an optimiz...
In sodium fast reactor designs, the fuel related inherent negative reactivity feedback is accomplish...
A comparative evaluation of minor actinide (MA) transmutation property was performed for various fas...
This paper describes the neutron transport calculations for the sodium-cooled fast reactors by using...
International audienceThe reduction of the initial excess reactivity in fast reactor cores would enh...
International audienceMinor actinides transmutation is a solution to decrease the long-term radiotox...
According to the Generation IV International Forum Technology Roadmap, Sodium Fast Reactors (SFR) co...
International audienceThe small modular sodium-cooled fast reactor (SMSFR) is an important component...
This research developed a design of an innovative sodium-cooled fast reactor (SFR) for minor actinid...
This paper shows that lead-cooled and sodium-cooled fast reactors (LFRs and SFRs) can preferentially...
Neutron transport and depletion calculations are performed in combination with various nuclear data ...
AbstractTo fulfill safety of fast sodium reactors in a beyond design-basis accident (BDBA) like unpr...
In this paper, neutronics and severe safety characteristics of Lead-cooled Fast Reactor (LFR) and So...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
The sensitivity of two operational output parameters, criticality and isotopic composition during bu...
This paper presents a new design for a small modular sodium-cooled fast reactor core with an optimiz...
In sodium fast reactor designs, the fuel related inherent negative reactivity feedback is accomplish...
A comparative evaluation of minor actinide (MA) transmutation property was performed for various fas...
This paper describes the neutron transport calculations for the sodium-cooled fast reactors by using...