Thorium cycle models into DIONISIO code: Species, thermomechanical behaviour and fission gas release

•A thorium cycle model was developed to include in DIONISIO fuel performance code.•The model shows an acceptable performance in comparison with results from CONDOR neutronic code.•The main thermomechanical properties of Thorium based nuclear fuel were simulated.•An existing FGR model was modified to...

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Bibliographic Details
Published in:Journal of nuclear materials 2021-12, Vol.557, p.153279, Article 153279
Main Authors: Loza Peralta, M.E., Gonzalez, M.E., Villarino, E., Bea, E.A., Soba, A.
Format: Article
Language:English
Subjects:
Computer applications
CONDOR code
DIONISIO code
Fission
Fission gas release
Mathematical models
Mechanical properties
MOX nuclear fuel
Nuclides
Parameter modification
Plutonium dioxide
Species
Thermomechanical properties
Thorium
Thorium cycle
Thorium oxides
Thorium thermomechanical properties
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Summary:•A thorium cycle model was developed to include in DIONISIO fuel performance code.•The model shows an acceptable performance in comparison with results from CONDOR neutronic code.•The main thermomechanical properties of Thorium based nuclear fuel were simulated.•An existing FGR model was modified to simulate the phenomena for Thorium based nuclear fuel.•All the mentioned models shows an acceptable performance in comparison with experimental data. In this work we present the main developments made to include the thorium cycle in the DIONISIO fuel code. For this, models for species evolution, thermomechanical behaviour and fission gas release development are incorporated. First of all, a simplified neutronic behaviour model was developed, which adds the capability of simulating the whole cycle at the least possible computational cost. We start from the balance of nuclides in the thorium chain, considering fresh ThO2 mixed with PuO2, which works as fissile species for the initial stages of operation. This simple model shows an acceptable performance in comparison with results from dedicated neutronic codes like CONDOR. Afterwards, the main thermal and mechanical parameters were adapted for thorium mixed oxide materials. For fission gas release, an existing model based on diffusion equations was also modified on the same way as thermomechanical parameters. Finally, results of the whole code with the included modifications were compared to some experiments over mixed fuels (Th,Pu)O2 andl (Th,U)O2.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2021.153279