Development of core fuel management code system for CANDU reactor based on coupled neutronics and thermal-hydraulic advanced nodal method

Annals of Nuclear Energy

Volumn 31, Issue 10, 2004, Pages 1083-1100

  Huo, Xiaodong ^a   Xie, Zhongsheng ^a   Liao, Chengkui ^b  

^a XI'AN JIAOTONG UNIVERSITY   (China)

^b Shanghai Nuclear Engineering Research and Design Institute   (China)

Author keywords

[No Author keywords available]

Indexed keywords

CODES (SYMBOLS); COMPUTER SOFTWARE; COOLANTS; HEAVY WATER REACTORS; HYDRAULICS; MATHEMATICAL MODELS; NEUTRONS;

FUEL MANAGEMENT; NEUTRONICS;

NUCLEAR FUELS;

EID: 1642633260     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2004.02.003     Document Type: Article

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