Monte Carlo codes are powerful and accurate tools for reactor core calculations. For coupled core-evolution applications, however, they remain rather demanding on calculation time because of the sheer number of reaction rates required for the evolution calculation. To make Monte Carlo burnup codes more efficient, we must therefore optimize reaction rate calculation to reduce calculation time without loss of accuracy. In the optimal situation, the calculation time of the Monte Carlo burnup code should be as close as possible to that of the basic Monte Carlo simulation. Through a deep analysis of the Monte Carlo simulation process as implemented in MCNP or MCNPX, we have developed an optimum approach called hereafter the multigroup binning ap...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Inline algorithms have been proposed for coupling Monte Carlo neutron transport solvers with several...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
Shells coupling Monte-Carlo transport and deterministic depletion codes are extensively used in the ...
The modeling of the component material composition during and after the fusion energy power plant's ...
The modeling of the component material composition during and after the fusion energy power plant's ...
The generation of reaction rates within Monte-Carlo (MC) transport codes can be accomplished via 1) ...
The generation of reaction rates within Monte-Carlo (MC) transport codes can be accomplished via 1) ...
International audienceThe modeling of the component material composition during and after the fusion...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
Coupled Monte Carlo depletion systems provide a versatile and an accurate tool for analyzing advance...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion t...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Inline algorithms have been proposed for coupling Monte Carlo neutron transport solvers with several...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
Shells coupling Monte-Carlo transport and deterministic depletion codes are extensively used in the ...
The modeling of the component material composition during and after the fusion energy power plant's ...
The modeling of the component material composition during and after the fusion energy power plant's ...
The generation of reaction rates within Monte-Carlo (MC) transport codes can be accomplished via 1) ...
The generation of reaction rates within Monte-Carlo (MC) transport codes can be accomplished via 1) ...
International audienceThe modeling of the component material composition during and after the fusion...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
Coupled Monte Carlo depletion systems provide a versatile and an accurate tool for analyzing advance...
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion t...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Allowing Monte Carlo (MC) codes to perform fuel cycle calculations requires coupling to a point depl...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Inline algorithms have been proposed for coupling Monte Carlo neutron transport solvers with several...