This article describes the implementation of a burnup scheme with coupled fuel behavior feedback into the Monte Carlo code Serpent 2. The new capabilities are applied to estimate the effects of typical simplifications concerning the fuel temperature distribution in the burnup history part of group constant generation. A set of group constants are generated for an assembly of the EPR by executing the burnup history calculation with either an assembly wide constant effective fuel temperature or realistic pin-wise fuel temperature distributions provided by a coupling to an external fuel performance solver. The differences in nuclide concentrations and generated group constants are quantified and the benefits of using a separate effective tempe...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
We extend the multi-physics capabilities of the Serpent 2 Monte Carlo code to coupled burnup calcula...
This paper presents two topics related to the burnup calculation capabilities in the Serpent 2 Monte...
Serpent is the new version of the PSG continuous-energyMonte Carlo reactor physics code, developed a...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
One of the main advantages of the continuous-energy Monte Carlo method is its versatility and the ca...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
This paper presents two separate nuclear data related features recently implemented in the Serpent M...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
Using the new collision history implementation in Serpent, a perturbation-based burn-up coupling sch...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
We extend the multi-physics capabilities of the Serpent 2 Monte Carlo code to coupled burnup calcula...
This paper presents two topics related to the burnup calculation capabilities in the Serpent 2 Monte...
Serpent is the new version of the PSG continuous-energyMonte Carlo reactor physics code, developed a...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
One of the main advantages of the continuous-energy Monte Carlo method is its versatility and the ca...
This paper describes the recent developments in the multi-physics capabilities of the Serpent Monte ...
This paper presents two separate nuclear data related features recently implemented in the Serpent M...
In nuclear reactor analysis, a relevant challenge is to achieve a suitable global description of nuc...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
Using the new collision history implementation in Serpent, a perturbation-based burn-up coupling sch...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
Nowadays, different multi-physics approaches are available, in order to improve the reactor safety a...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...