Degraded core reflood: Present understanding and impact on LWRs

Nuclear Engineering and Design

Volumn 237, Issue 24, 2007, Pages 2315-2321

  Hering, Wolfgang ^a   Homann, Christoph ^a  

^a KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

FLOW RATE; FUELS; PRESSURIZED WATER REACTORS; THERMAL EFFECTS;

CORE REFLOOD; SINGLE ROD EXPERIMENTS; ZIRCALOY;

NUCLEAR ENGINEERING;

EID: 36348974141     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2007.04.017     Document Type: Article

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