Development of a safety analysis code for molten salt reactors

Nuclear Engineering and Design

Volumn 239, Issue 12, 2009, Pages 2778-2785

  Zhang, Dalin ^a,b   Qiu, Suizheng ^a,b   Su, Guanghui ^a,b  

^a XI'AN JIAOTONG UNIVERSITY   (China)

^b XI'AN JIAOTONG UNIVERSITY   (China)

Author keywords

[No Author keywords available]

Indexed keywords

CHARACTERISTIC ANALYSIS; CODE COUPLING; FLOW EFFECTS; GENERATION IV; HEAT TRANSFER MODEL; MOLTEN SALT; MOLTEN SALT REACTOR; POINT KINETICS; SAFETY ANALYSIS CODES; SOLID-FUEL; STABLE REACTORS; TRANSIENT CONDITIONS; UNPROTECTED TRANSIENT OVERPOWER;

CONCEPTUAL DESIGN; FUELS; FUSED SALTS; HEAT TRANSFER; NUCLEAR REACTORS;

MOLTEN MATERIALS;

EID: 70449647107     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.08.020     Document Type: Article

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