Laboratory for Simulation and Modelling (LSM)

HPNALGS

The PSI Laboratory for Simulation and Modelling develops numerical and computational capabilities for advanced nuclear systems, advanced particle accelerators, reacting and non-reacting fluid dynamics.

The topical areas of the Laboratory for Simulation and Modelling covers a broad spectrum of scientific disciplines such as

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Dr. Ioannis (John) Mantzaras

Fellow Award for Dr. Mantzaras

The prestigious Fellow Award “Fellow of The Combustion Institute” was allotted to Dr. Mantzaras for “Pioneering Experimental and Modeling Research in Hetero-/Homogeneous and Catalytic Combustion”. The combustion activities at LSM emphasize on non-intrusive laser-based measurements in a high-pressure optically accessible catalytic reactor, while the modeling activities encompass advanced multidimensional numerical simulations and theoretical work based on activation energy asymptotics.

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Dr. Andreas Adelmann
•Technologies d’avenir
•6 min

Modéliser et simuler: un bon retour sur investissement

Biologie
Energie nucléaire

En combinant théorie, modélisation et calculs à haute performance, les chercheurs du Laboratoire de simulation et modélisation de l’Institut Paul Scherrer PSI résolvent les problèmes les plus complexes. De puissants ordinateurs leur permettent de simuler aussi bien les molécules les plus minuscules que les grandes installations de recherche.

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  • Albà A, Adelmann A, Rochman D
    Uncertainty quantification of spent nuclear fuel with multifidelity Monte Carlo
    Annals of Nuclear Energy. 2025; 211: 110892 (17 pp.). https://doi.org/10.1016/j.anucene.2024.110892
    DORA PSI
  • Berry L, Vasiliev A, Rochman D, Hursin M, Frankl M, Ferroukhi H
    Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions
    Annals of Nuclear Energy. 2025; 211: 110939 (14 pp.). https://doi.org/10.1016/j.anucene.2024.110939
    DORA PSI
  • Cherezov A, Vasiliev A, Ferroukhi H
    Application of backward differential formula and Anderson's method for multigroup diffusion transient equation
    Annals of Nuclear Energy. 2025; 210: 110837 (19 pp.). https://doi.org/10.1016/j.anucene.2024.110837
    DORA PSI
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