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SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

D. Pizzocri, T. Barani, L. Luzzi

2020Journal of Nuclear Materials80 citationsDOIOpen Access PDF

Abstract

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 inter-granular 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 – verification of different numerical solvers is also showcased in this work.

Topics & Concepts

BurnupComputer scienceNuclear engineeringScale (ratio)Source codeWork (physics)Bridging (networking)Code (set theory)Consistency (knowledge bases)SimulationComputational scienceMechanical engineeringEngineeringPhysicsOperating systemComputer networkArtificial intelligenceProgramming languageSet (abstract data type)Quantum mechanicsNuclear Materials and PropertiesNuclear reactor physics and engineeringRadioactive element chemistry and processing
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