Fig.1: Cumulative electricity requirement for the European fleet between 2018 and 2100
Fig.1: Cumulative electricity requirement for the European fleet between 2018 and 2100.

“JF” = fossil kerosene scenario. “syn-JF” = synthetic kerosene scenario (100% by 2063). “Flight-CO2 neutral” = only warming from kerosene combustion is mitigated. “Warming-neutral” = the warming caused by the fleet is stabilized from 2050 on. “Climate-neutral” = the warming impact between 2018 and 2100 is entirely mitigated. “DACCS” = Direct Air Capture with Carbon Storage.

PSI Center for Nuclear Engineering and Sciences

Safety of currently operating light-water reactors, safety characteristics of future reactor concepts, and long-term safety of deep geological repositories for nuclear wastes are the main research topics at the PSI Center for Nuclear Engineering and Sciences.

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Approximate Computing for Nuclear Reactor Simulations

During the last decades, computing power has been subject to tremendous progress due to the shrinking of transistor size as predicted by Moore’s law. However, as we approach the physical limits of this scaling, alternative techniques have to be deployed to increase computing performance. In this regard, the next big advance is envisioned to be the usage of approximate computing hardware based on field-programmable gate arrays and/or digital-analogue in-memory circuits. Such approximate computing can provide disproportional gain (x1000) in energy efficiency and/or execution time for acceptable loss of simulation accuracy. This could be highly beneficial in order to accelerate computational intensive simulations such as reactor core analyses with higher resolution multi-physics models. On the other hand, the execution of programming codes on low-precision hardware may result in inadequate outcomes due to quality degradation and/or algorithm divergence. To address these questions, studies on the stability and the performance of advanced reactor simulation algorithms as function of reduced floating-point arithmetic precision are being conducted at the laboratory for reactor physics and thermal-hydraulics. Results obtained so far indicate a large room for the acceleration of nuclear engineering applications using mixed-precision hardware. Therefore, research is now being enlarged towards assessing multiprecision computing methods for reactor core simulations with higher spatial resolution.

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  • Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
    The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions
    Nuclear Engineering and Design. 2024; 416: 112815 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112815
    DORA PSI
  • Albà A, Adelmann A, Münster L, Rochman D, Boiger R
    Fast uncertainty quantification of spent nuclear fuel with neural networks
    Annals of Nuclear Energy. 2024; 196: 110204 (8 pp.). https://doi.org/10.1016/j.anucene.2023.110204
    DORA PSI
  • Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Rada AP, et al.
    A segmented total energy detector (sTED) optimized for (n, γ) cross-section measurements at n_TOF EAR2
    Radiation Physics and Chemistry. 2024; 217: 111525 (11 pp.). https://doi.org/10.1016/j.radphyschem.2024.111525
    DORA PSI
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