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

被引：4

作者：

Angelucci, Michela ^{[1
]}

Herranz, Luis E. ^{[2
]}

Paci, Sandro ^{[1
]}

机构：

[1] Univ Pisa UNIPI, Dept Ind & Civil Engn, I-56122 Pisa, Italy

[2] Ctr Invest Energet Medioambientales & Tecnol CIEMA, Madrid 28040, Spain

来源：

NUCLEAR ENGINEERING AND DESIGN | 2024年 / 419卷

关键词：

Dry cask; Spent fuel; Off -normal conditions; Accidental conditions; MELCOR; Nuclear safety; STORAGE; METHODOLOGY; PERFORMANCE;

D O I：

10.1016/j.nucengdes.2024.112992

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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.

引用

页数：11

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