Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants

Safety analyses of nuclear power plant accidents are a key tool in demonstration of nuclear safety and reliability. The chain of the safety analyses comprises several follow-up activities like neutronic core calculation, primary system simulation and containment response to a loss-of-coolant acciden...

Ausführliche Beschreibung

Bibliographische Detailangaben

Veröffentlicht in:	Kerntechnik (1987) 2023-02, Vol.88 (1), p.1-12
Hauptverfasser:	Kecek, Adam, Denk, Lubomír, Zamakhaeva, Iana
Format:	Artikel
Sprache:	eng
Schlagworte:	COCOSYS containment iodine LOCA validation
Online-Zugang:	Volltext
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