PSI - Issue 77

Enrique Gómez et al. / Procedia Structural Integrity 77 (2026) 49–55 Enrique Gómez et al. / Structural Integrity Procedia 00 (2026) 000–000

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Figure 3. FAD analyses of the different conditions shown in Table 5.

4. Conclusions This work presents an example of the structural integrity analysis for the shells of an ENUN spent fuel cask. The assessment is based on BS7910 Option 1 analysis, with the material properties established by the corresponding material specification and the loading cases derived from the nuclear regulations. The results show that the cask operation is safe in both Normal Operating Conditions (NOC) and Accidental Conditions (AC), also complying with minimum safety factors established by the nuclear industry for this kind of components and applications. The analysis presented here is a preliminary step to the activities to be developed within the framework of the COSME project, whose main objective is to evaluate and rule out non-ductile fracture failure in the containment barrier of ENUN casks by using both the fracture mechanics principles included in the ASME Code and the real mechanical properties of the cask materials. Acknowledgements This publication is part of the project “COSME- Evaluación de integridad estructural de contenedores basada en código ASME y propiedades mecánicas reales” funded by Consejo de Seguridad Nuclear (CSN)- Spanish Nuclear Safety Council. References ASME Boiler and Pressure Vessel Code. Section II, Materials. ASME, New York, 2023. ASME Boiler and Pressure Vessel Code Section III, Rules for Construction of Nuclear Facility Components. ASME, New York, 2023. ASME Boiler and Pressure Vessel Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. ASME, New York, 2023. BS 7910:2019, Guide to methods for assessing the acceptability of flaws in metallic structures. British Standard Institution, London, 2019. Dillstroem, P., Bergman, M., Brickstad, B., Weilin Zang, Sattari-Far, I., Andersson, P., Sund, G., Dahlberg, L., Nilsson, F., 2008. A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook. Swedish Radiation Safety Authority, Stockholm, Sweden. European Agreement concerning the International Carriage of Dangerous Goods by Road (ADR). United Nations, New York and Geneva, 2025 IAEA Safety Standards No. SSG-26, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. IAEA, Vienna, 2018.