Single-phase CFD applicability for estimating fluid hot-spot locations in a 5 × 5 fuel rod bundle

Nuclear Engineering and Design

Volumn 236, Issue 11, 2006, Pages 1149-1154

  Ikeda, Kazuo ^a   Makino, Yasushi ^b   Hoshi, Masaya ^b  

^a Nuclear Development Corporation   (Japan)

^b MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; ENTHALPY; HEAT FLUX; MATHEMATICAL MODELS; NUCLEATE BOILING; PRESSURE EFFECTS;

DEPARTURE FROM NUCLEATE BOILING (DNB) TEST; PRESSURE LOSS; SPACER GRIDS;

COMPUTATIONAL FLUID DYNAMICS;

EID: 33646111693     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.11.006     Document Type: Article

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8. Teshima H., Ikeda K., Kobayashi H., Mori M., and Hoshi M. Investigation of PWR fuel rod vibration induced by cross-flow. Proceedings of 15th SMiRT. Seoul, Korea (1999)