Preliminary transient thermal-hydraulic analysis for new coated un and UC fuel options in SCWR

Progress in Nuclear Energy

Volumn 71, Issue , 2014, Pages 152-159

  Zhao, Hao ^a   Zhu, Dahuan ^a   Chaudri, Khurrum Saleem ^a   Qiu, Suizheng ^a   Tian, Wenxi ^a   Su, Guanghui ^a  

^a XI'AN JIAOTONG UNIVERSITY   (China)

Author keywords

Nuclear fuel; SCWR; Thermal hydraulic; Transient analysis; Uranium carbide (UC); Uranium nitride (UN)

Indexed keywords

LOW THERMAL CONDUCTIVITY; OPERATING TEMPERATURE RANGES; SCWR; SILICON CARBIDES (SIC); THERMAL HYDRAULICS; TRANSIENT THERMAL-HYDRAULIC; URANIUM NITRIDE; XI'AN JIAOTONG UNIVERSITY;

ACCIDENTS; DESIGN; FUELS; NUCLEAR FUELS; SILICON CARBIDE; TRANSIENT ANALYSIS; URANIUM; URANIUM CARBIDE; ZIRCONIUM COMPOUNDS;

WATER COOLED REACTORS;

EID: 84891409342     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2013.11.008     Document Type: Article

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