Add to ORKGVe výpočetním kódu TRITON a ORIGEN-ARP byl vytvořen model výpočtu paliva Gd-2M+, pro který byl proveden odhad chyby výpočtu. Na základě tohoto modelu byl stanoven vliv provozních a výrobních nejistot na množství jednotlivých nuklidů ve vyhořelém palivu. Rovněž byl stanoven vliv těchto nejistot na koeficient násobení.By applying calculation sequences ORIGEN-ARP and TRITON depletion model of Gd-2M+ fuel was made. Uncertainities of this calcalation by comparison with experimental data for both calculation sequences were determined. Effects of operational and manufactoring uncertainities on depletion of Gd-2M+ fuel were determined. Effect of thess uncertainities on the multiplication factor was also specified
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to comput...
The work described in this report presents sensitivity and uncertainty calculations in EU project EU...
In the depletion calculation of the nuclear fuel, the uncertainty is of utmost importance, as it aff...
In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation c...
In this paper, we present an uncertainty methodology based on a statistical approach, for assessing ...
Waste packages often contain wastes forms of different types of spent fuels and of various operation...
Nuclear data-induced uncertainties of infinite neutron multiplication factors (k) during fuel deplet...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
International audienceFuel cycle scenarios are "boundary objects" providing an opportunity to bring ...
Nuclear data uncertainty propagation can be analyzed for various applications. Uncertainty of neutro...
Presently, a criticality safety evaluation methodology for the final geological disposal of Swiss sp...
The material composition of nuclear fuel changes constantly due to nuclides transforming to other nu...
Two fuel assemblies, one belonging to the Takahama-3 PWR and the other to the Fukushima-Daini-2 BWR,...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to comput...
The work described in this report presents sensitivity and uncertainty calculations in EU project EU...
In the depletion calculation of the nuclear fuel, the uncertainty is of utmost importance, as it aff...
In this work, the objective is to perform an uncertainty analysis on a MYRRHA -Rev.1.6 irradiation c...
In this paper, we present an uncertainty methodology based on a statistical approach, for assessing ...
Waste packages often contain wastes forms of different types of spent fuels and of various operation...
Nuclear data-induced uncertainties of infinite neutron multiplication factors (k) during fuel deplet...
The key papers on estimating the uncertainties in nuclear data deal with the influence of these unce...
International audienceFuel cycle scenarios are "boundary objects" providing an opportunity to bring ...
Nuclear data uncertainty propagation can be analyzed for various applications. Uncertainty of neutro...
Presently, a criticality safety evaluation methodology for the final geological disposal of Swiss sp...
The material composition of nuclear fuel changes constantly due to nuclides transforming to other nu...
Two fuel assemblies, one belonging to the Takahama-3 PWR and the other to the Fukushima-Daini-2 BWR,...
The mathematical modelling and evaluation of the nuclear fuel while burning in nuclear reactors is o...
Knowledge of spent nuclear fuel (SNF) source term (decay heat, reactivity, nuclide inventory and oth...
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to comput...
The work described in this report presents sensitivity and uncertainty calculations in EU project EU...