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

Róbert Farkas / Zoltán Hózer / Zoltán Kis / Erzsébet Perez-Feró / Márton Király / Márta Horváth / Tamás Novotny / Péter Szabó / Tamás Bubonyi

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.

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

Róbert Farkas / Zoltán Hózer / Zoltán Kis / Erzsébet Perez-Feró / Márton Király / Márta Horváth / Tamás Novotny / Péter Szabó / Tamás Bubonyi

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.

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

Róbert Farkas / Zoltán Hózer / Zoltán Kis / Erzsébet Perez-Feró / Márton Király / Márta Horváth / Tamás Novotny / Péter Szabó / Tamás Bubonyi

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.

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Titel:

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

Beteiligte:

Róbert Farkas (Autor:in) / Zoltán Hózer (Autor:in) / Zoltán Kis (Autor:in) / Erzsébet Perez-Feró (Autor:in) / Márton Király (Autor:in) / Márta Horváth (Autor:in) / Tamás Novotny (Autor:in) / Péter Szabó (Autor:in) / Tamás Bubonyi (Autor:in)

Erschienen in:

Nuclear Materials and Energy, Vol 40, Iss , Pp 101695- (2024)

Erscheinungsdatum:

2024

ISSN:

DOI:

https://doi.org/10.1016/j.nme.2024.101695

Medientyp:

Aufsatz (Zeitschrift)

Format:

Elektronische Ressource

Sprache:

Unbekannt

Schlagwörter:

Nuclear engineering. Atomic power , TK9001-9401

Metadata by DOAJ is licensed under CC BY-SA 1.0

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