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  1. sciencedirect.com

    Dec 1, 2024Given the numerical foundation of the code, it is applicable to both stationary and transient conditions. Following a recent work outlining the standalone SCIANTIX (version 2.0) performance and its separate-effect validation database, we present its performance when coupled with fuel performance codes to simulate light water reactor fuel rods.
  2. semanticscholar.org

    Jul 1, 2024DOI: 10.1016/j.jnucmat.2024.155305 Corpus ID: 271636751; Integral-scale validation of the SCIANTIX 2.0 code for Light Water Reactor fuel rods @article{Zullo2024IntegralscaleVO, title={Integral-scale validation of the SCIANTIX 2.0 code for Light Water Reactor fuel rods}, author={G. Zullo and Davide Pizzocri and Alessandro Scolaro and Paul Van Uffelen and F. Feria and L.E. Herranz and L. Luzzi ...
  3. Zullo et al, The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments. Zullo et al, Two-phase modelling for fission gas sweeping in restructuring nuclear oxide fuel. Zullo et al, Integral-scale validation of the SCIANTIX code for Light Water Reactor fuel rods. Verma et al, Extending the ...
  4. sciencedirect.com

    Dec 15, 2023This work describes the status of SCIANTIX, a 0D, open-source code designed to model inert gas behaviour within nuclear fuel at the grain scale. The code is hosted online at [66], and it can be used both as a standalone module or coupled with integral codes, e.g., fuel performance codes. Since its first release, the code architecture has been ...
  5. The OperaHPC project aims to improve the numerical capabilities of 3D fuel performance modelling as part of its strategic objectives. To achieve this goal, an open-source approach has been chosen for the tools developed in the framework of the project, namely MMM and OFFBEAT, the latter coupled to the SCIANTIX code.
  6. researchgate.net

    life-limiting factor for the operation of nuclear fuel in light water and fast reactors [1,3,11,12]. For this reason, the modelling of fission gas behaviour is a crucial aspect in fuel ...
  7. Fuel performance codes, which enable the simulation of the behaviour of the fuel elements in reactor, are now an essential component of the design, licensing and safety assessment of nuclear fuels. ... Develop open-source 3D high-fidelity simulation tools for the thermomechanical behaviour of nuclear fuel rods under irradiation.
  8. sciencedirect.com

    SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes ... The database consists in measurements performed on uranium dioxide Advanced Gas Reactor samples of fuel rods irradiated up to burnup between 9 and 21 GWd/t UO2 in the Halden reactor. After the base irradiation, rods ...
  9. papers.ssrn.com

    Feb 29, 2024Given the numerical foundation of the code, the code is also naturally applicable to both stationary and transient conditions. Following a recent work outlining the standalone code performance and its separate-effect validation database, here we present the performance of SCIANTIX (version 2.0) when coupled with fuel performance codes to ...
  10. semanticscholar.org

    Integral-scale validation of the SCIANTIX 2.0 code for Light Water Reactor fuel rods. G. Zullo D. Pizzocri +4 authors L. Luzzi. Engineering, Physics ... FRAPCON-3 is a FORTRAN IV computer code that calculates the steady-state response of light water reactor fuel rods during long-term burnup. The code calculates the temperature, ...

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