The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical Research Centre of Finland since 2004, and is currently used in over 100 universities and research organizations around the world. This paper presents the brief history of the project, together with the currently available methods and capabilities and plans for future work. Typical user applications are introduced in the form of a summary review on Serpent-related publications over the past few years
Continuous improvement in Nuclear Industry Safety Standards and reactor designer’s and operator’s co...
monteburns, a burnup computer code that uses the Monte Carlo technique, was developed at Los Alamos ...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
Serpent is the new version of the PSG continuous-energyMonte Carlo reactor physics code, developed a...
This paper presents two topics related to the burnup calculation capabilities in the Serpent 2 Monte...
The PSG2 / Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT sin...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
This paper presents two separate nuclear data related features recently implemented in the Serpent M...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
One of the main advantages of the continuous-energy Monte Carlo method is its versatility and the ca...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
This paper is mainly devoted to the proof-of-principle implementation of the SERPENT code for the si...
WOS: 000323402800004In this study, burnup calculations have been performed for a sodium cooled Accel...
Continuous improvement in Nuclear Industry Safety Standards and reactor designer’s and operator’s co...
monteburns, a burnup computer code that uses the Monte Carlo technique, was developed at Los Alamos ...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
The Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT Technical ...
Serpent is the new version of the PSG continuous-energyMonte Carlo reactor physics code, developed a...
This paper presents two topics related to the burnup calculation capabilities in the Serpent 2 Monte...
The PSG2 / Serpent Monte Carlo reactor physics burnup calculation code has been developed at VTT sin...
This paper is a general overview of the Serpent Monte Carlo reactor physics burnup calculation code....
This paper presents two separate nuclear data related features recently implemented in the Serpent M...
This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURN...
One of the main advantages of the continuous-energy Monte Carlo method is its versatility and the ca...
This article describes the implementation of a burnup scheme with coupled fuel behavior feedback int...
This paper is mainly devoted to the proof-of-principle implementation of the SERPENT code for the si...
WOS: 000323402800004In this study, burnup calculations have been performed for a sodium cooled Accel...
Continuous improvement in Nuclear Industry Safety Standards and reactor designer’s and operator’s co...
monteburns, a burnup computer code that uses the Monte Carlo technique, was developed at Los Alamos ...
Several computer codes have been developed to perform nuclear burnup calculations over the past few ...