Critical heat flux in a vertical annulus under low upward flow and near atmospheric pressure

Journal of Nuclear Science and Technology

Volumn 34, Issue 6, 1997, Pages 559-570

  Schoesse, Thomas ^a   Aritomi, Masanori ^a   Kataoka, Yoshiaki ^b   Lee, Sang Ryoul ^a   Yoshioka, Yuzuru ^c   Chung, Moon Ki ^d  

^a TOKYO INSTITUTE OF TECHNOLOGY   (Japan)

^b MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^c Mitoshiro Bldg   (Japan)

^d Korea Atomic Energy Research Institute   (South Korea)

Author keywords

Annular flow; Boiling transition; Churn flow; Comparative evaluations errors; Critical heat flux; Flow fluctuation; Flow pattern; Future boiling water reactor; Two phase flow

Indexed keywords

BOILING LIQUIDS; CORRELATION METHODS; ERROR ANALYSIS; FLOW PATTERNS; FUEL PUMPS; HEAT FLUX; HYDRAULICS; REACTOR CORES; ROTATIONAL FLOW;

CRITICAL HEAT FLUX (CHF);

BOILING WATER REACTORS;

EID: 0031166006     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1997.9733709     Document Type: Article

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