Details

Autor(en) / Beteiligte

• Angelucci, Michela
• Herranz, Luis E.
• Paci, Sandro

Titel

On the behavior of a concrete-based dry cask for spent nuclear fuel in off-normal and accidental conditions

Ist Teil von

• Nuclear engineering and design, 2024-04, Vol.419, p.112992, Article 112992

Ort / Verlag

Elsevier B.V

Erscheinungsjahr

2024

Quelle

Access via ScienceDirect (Elsevier)

Beschreibungen/Notizen

• •The safe storage of Spent Nuclear Fuel (SNF) within a dry cask system must be guaranteed for any operating condition.•The influence of a partial to complete blockage of air inlet openings on the PCT is assessed for the HI-STORM 100S system.•The cooling and the safe storage of the SNF seem to be ensured also in out-of-the ordinary situations.•The results from the adiabatic (most extreme) case indicate the importance of a tempestive accident management.•MELCOR showed good adaptability and flexibility, even in simulating scenarios out of its natural domain of application. The safe storage of Spent Nuclear Fuel (SNF) within a dry cask system must be guaranteed for any operating condition. In particular, the Peak Cladding Temperature (PCT) is currently employed as a measure of the fuel integrity in normal conditions. The same fuel integrity has to be ensured also in off-normal and accidental conditions by keeping the PCT below the regulatory limits. In this regard, the work proposed in this paper aims at evaluating the performance of a concrete-based dry cask in off-normal and accidental conditions. More specifically, the influence of a partial to complete blockage of the air inlet openings on the PCT is assessed by means of a MELCOR model of the HI-STORM 100S cask. Attention is also paid to the temperature of the external concrete cask in order to check the integrity of the concrete itself.