Add to ORKGMonte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to compute various quantities of interest, including isotopic compositions of used fuel.1 The TRITON control module, available in the SCALE 5.1 code system, can perform three-dimensional (3-D) depletion calculations using either the KENO V.a or KENO-VI Monte Carl
In this work, the depletion capability implemented in Monte Carlo code MCS is investigated to predic...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...
The purpose of this calculation report is to document the comparison to measurement of the isotopic ...
Monte Carlo methods are beginning to be used for three dimensional fuel depletion analyses to comput...
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to comput...
Recent developments in spent fuel characterization methods have involved the development of several ...
In the depletion calculation of the nuclear fuel, the uncertainty is of utmost importance, as it aff...
As part of the validation of the three-dimensional (3D) continuous-energy neutron-photon transport M...
Two independent methods using both deterministic and Monte Carlo methods are used to perform depleti...
Acquisition and analysis of experimental isotopic assay data are essential for validating computer c...
This paper describes a new three-dimensional (3-D) Monte Carlo-based depletion sequence that is bein...
Knowledge of fuel composition as a function of irradiation time is of paramount importance both for ...
At the present time, 2D depletion codes are the state of the art. KENOREST has been specially develo...
Within an energy system where nuclear reactors will likely play a critical role, it is fundamental t...
Depletion calculations have been performed for the McClellan reactor history from January 1990 throu...
In this work, the depletion capability implemented in Monte Carlo code MCS is investigated to predic...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...
The purpose of this calculation report is to document the comparison to measurement of the isotopic ...
Monte Carlo methods are beginning to be used for three dimensional fuel depletion analyses to comput...
Monte Carlo methods are beginning to be used for three-dimensional fuel depletion analyses to comput...
Recent developments in spent fuel characterization methods have involved the development of several ...
In the depletion calculation of the nuclear fuel, the uncertainty is of utmost importance, as it aff...
As part of the validation of the three-dimensional (3D) continuous-energy neutron-photon transport M...
Two independent methods using both deterministic and Monte Carlo methods are used to perform depleti...
Acquisition and analysis of experimental isotopic assay data are essential for validating computer c...
This paper describes a new three-dimensional (3-D) Monte Carlo-based depletion sequence that is bein...
Knowledge of fuel composition as a function of irradiation time is of paramount importance both for ...
At the present time, 2D depletion codes are the state of the art. KENOREST has been specially develo...
Within an energy system where nuclear reactors will likely play a critical role, it is fundamental t...
Depletion calculations have been performed for the McClellan reactor history from January 1990 throu...
In this work, the depletion capability implemented in Monte Carlo code MCS is investigated to predic...
In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity method...
The purpose of this calculation report is to document the comparison to measurement of the isotopic ...