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Volumn 35, Issue 12, 1998, Pages 943-951

Improvement of critical heat flux correlation for research reactors using plate-type fuel

Author keywords

Core flow reversal; Counter current flow limitation; Critical heat flux; Flooding condition; Inlet subcooling; Natural convection; Plate type fuel elements; Research reactors; Vertical rectangular channels

Indexed keywords

ACCIDENT PREVENTION; ATMOSPHERIC PRESSURE; CHANNEL FLOW; COOLING; CORRELATION METHODS; HEAT FLUX; LOSS OF COOLANT ACCIDENTS; NATURAL CONVECTION; NUCLEAR FUEL ELEMENTS; REACTOR CORES;

EID: 0032258729     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1998.9733966     Document Type: Article
Times cited : (38)

References (10)
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  • 2
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  • 3
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    • A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors
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    • Sudo, Y.1    Kaminaga, M.2
  • 4
    • 0022099750 scopus 로고
    • Core ther-mohydraulic design with 20% LEU fuel for upgraded research reactor JRR-3
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    • Kaminaga, M.1    Yamamoto, K.2    Watanabe, S.3
  • 6
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    • Safety analysis of JMTR-LEU cores (1)— Reactivity initiated accident analysis
    • Nagaoka Y., Komukai, B., Sakurai, F., Saito, M., Fu-tamura, Y.: Safety analysis of JMTR-LEU cores (1)— Reactivity initiated accident analysis, JAERI-M 92-095, (1992), [in Japanese]
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  • 8
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    • Experimental study of the critical heat flux in a narrow vertical rectangular channel
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  • 9
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.