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Long-term mechanical analysis of nuclear reactor containments

| 2024:1031 | Magnus Åhs, Richard Malm, Daniel Rydle, Christian Bernstone Manouchehr Hassanzadeh, Kim Calonius
The main purpose with this project has been to study reactor containments mechanical behaviour with time and to evaluate leakage during performed pressure tests.
Bild Till Webben Rapport 2024 1031

The report presents results of a benchmark, Vercors 2022, which Electricité de France organised. A multiphysics mathematical model has been developed applied to predict the long-term mechanical behaviour of a reactor containment. In addition, a leakage model has been developed that estimates the air leakage through a reactor containment when a pressure test is performed. The model is available to both designers and researchers. Many different parameters that give rise to deformations are included in the model like, temperature and moisture variations, pre-stressed tendons and creep according to Eurocode 2.

This analysis shows that the presented model underestimated the long-term deformations evaluated when compared with the actual observations at many of the analysed points. This underestimation applies to all examined structural components such as cylinder wall, gusset, dome, and raft structure.

The leakage model presented in this report is relatively simple yet provides a reasonably good agreement with measurements. It takes into account that air density varies with pressure and that the concrete air permeability increases at it dries.

Rapporter och publikationer

Här listas rapporter och resultatblad från programmet.

    • Rapport

    Methods for Locating Pool Liner Leakage at Nuclear Power Plants

    This report evaluates practical methods for localizing leakage-relevant defects in thin stainless-steel pool liners in nuclear facilities, with particular emphasis on inspection under water.

    |2026:1156Markus Nilsson, Lund university
    Pool Liner Leakage at Nuclear Power Plants
    • Rapport

    Determination of stresses in grouted strands of a reactor containment by a destructive test method

    The aim of this study is to analyze prestressed bonded tendons obtained through the decommissioning of Barsebäck nuclear power plant, to better understand the factors that influence their performance.

    |2025:1130Peter Lundqvist and Manouchehr Hassanzadeh, Sweco
    2025:1130 Rapportbild.png
    • Rapport

    Träinducerad korrosion på ingjuten tätplåt

    Projektet har utfört labbstudier med syfte att närmare undersöka de fenomen som sker vid initiering av en aktiv/passiv-cell inducerad av en ingjuten träbit på tätplåt.

    |2025:1123Jonas Engblom, Bertil Sandberg, Johan Ahlström
    Bild till webben 2025-1123
    • Rapport

    Shear Force Capacity of Existig Concrete Slabs, 2025:1102

    Shear force capacity in concrete slabs is crucial for structural integrity, especially in nuclear power plants where safety and reliability are paramount. In several cases low or sometimes insufficient shear force capacities have been observed in structural analyses of existing concrete slabs using modern codes. Understanding shear force capacity and how it has been treated in earlier codes helps ensure durability and safety, preventing structural failures.

    |2025:1102Lamis Ahmed
    2025 1102 Bild Webben (1)