DOAJ Open Access 2024

Simulation of loss-of-coolant accident with thin-walled cladding tubes

Róbert Farkas Zoltán Hózer Zoltán Kis Erzsébet Perez-Feró Márton Király +4 lainnya

Abstrak

A loss-of-coolant accident in a nuclear power plant was simulated in the CODEX-SLIM experiment. The electrically heated fuel rod bundle contained cladding material used at a VVER-440 power plant. The maximum temperature reached 900 °C and the experiment was terminated by water quenching. The condition of the bundle was investigated using non-destructive and destructive techniques. According to the experimental data, the fuel rods would maintain their integrity during a design basis loss-of-coolant accident.

Topik & Kata Kunci

Nuclear engineering. Atomic power

Penulis (9)

Róbert Farkas

Zoltán Hózer

Zoltán Kis

Erzsébet Perez-Feró

Márton Király

Márta Horváth

Tamás Novotny

Péter Szabó

Tamás Bubonyi

Format Sitasi

APA MLA BibTeX

Farkas, R., Hózer, Z., Kis, Z., Perez-Feró, E., Király, M., Horváth, M. et al. (2024). Simulation of loss-of-coolant accident with thin-walled cladding tubes. https://doi.org/10.1016/j.nme.2024.101695

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Informasi Jurnal

Tahun Terbit: 2024
Sumber Database: DOAJ
DOI: 10.1016/j.nme.2024.101695
Akses: Open Access ✓