Bridging lower length-scale calculations with the engineering-scale simulations of fuel performance codes requires the development of dedicated intermediate-scale codes. In this work, we present SCIANTIX, an open source 0D stand-alone computer code designed to be included/coupled as a module in existing fuel performance codes. The models currently available in SCIANTIX cover intra- and intergranular inert gas behaviour in UO2, and high burnup structure formation as well. Showcases of validation in both constant and transient conditions are presented in this work. As for the numerical treatment of the model equations, SCIANTIX is developed with full numerical consistency and entirely verified with the method of manufactured solutions - verif...
A formulation is proposed for modelling the process of intra-granular diffusion of fission gas durin...
This paper will present the modelling activities at various scales carried out and planned at ITU fo...
The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framewor...
Bridging lower length-scale calculations with the engineering-scale simulations of fuel performance ...
SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear fuel at the ...
The behaviour of the fission gas plays an important role in the fuel rod performance. In a previous ...
This paper concerns the modelling and the assessment of inert gas behaviour (IGB) in UO2 nuclear fue...
This final report summarizes the work performed by Politecnico di Milano (POLIMI) in the FUMAC Proje...
The goal of this deliverable is to present a synthesis of the model developments achieved during the...
Among the applications of the multiscale modelling approach in nuclear fuel rod performance, the cou...
In this paper, we present a novel, lightweight fuel behavior code, FINIX. FINIX provides an advanced...
This deliverable illustrates the new (2.0) version of the SCIANTIX meso-scale code, developed within...
Current modelling of inert gas behaviour (IGB) in fuel performance codes (FPCs) is mainly correlatio...
A formulation is proposed for modelling the process of intra-granular diffusion of fission gas durin...
In light of the importance of helium production in influencing the behaviour of fast reactor fuels, ...
A formulation is proposed for modelling the process of intra-granular diffusion of fission gas durin...
This paper will present the modelling activities at various scales carried out and planned at ITU fo...
The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framewor...
Bridging lower length-scale calculations with the engineering-scale simulations of fuel performance ...
SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear fuel at the ...
The behaviour of the fission gas plays an important role in the fuel rod performance. In a previous ...
This paper concerns the modelling and the assessment of inert gas behaviour (IGB) in UO2 nuclear fue...
This final report summarizes the work performed by Politecnico di Milano (POLIMI) in the FUMAC Proje...
The goal of this deliverable is to present a synthesis of the model developments achieved during the...
Among the applications of the multiscale modelling approach in nuclear fuel rod performance, the cou...
In this paper, we present a novel, lightweight fuel behavior code, FINIX. FINIX provides an advanced...
This deliverable illustrates the new (2.0) version of the SCIANTIX meso-scale code, developed within...
Current modelling of inert gas behaviour (IGB) in fuel performance codes (FPCs) is mainly correlatio...
A formulation is proposed for modelling the process of intra-granular diffusion of fission gas durin...
In light of the importance of helium production in influencing the behaviour of fast reactor fuels, ...
A formulation is proposed for modelling the process of intra-granular diffusion of fission gas durin...
This paper will present the modelling activities at various scales carried out and planned at ITU fo...
The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framewor...