New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Journal Article · Sat May 01 00:00:00 EDT 1993 · Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States)

DOI:https://doi.org/10.1115/1.2910695· OSTI ID:5898123

Sudo, Y ^[1]; Kaminaga, M ^[2]

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1. Japan Atomic Energy Research Inst., Oarai (Japan)
2. Japan Atomic Energy Research Inst., Tokai (Japan)

In this study, an investigation was carried out to identify the important parameters affecting critical heat flux (CHF) in rectangular channels, focusing on the effects of flow direction, channel inlet subcooling from 1 to 213 K, the channel outlet condition extending from subcooling of 0-74 K to quality of 0-1.0, pressure of 0.1 to 4 MPa, water mass flux of [minus]25,800 to +6250 kg/m[sup 2]s, and channel configuration. In particular, the effect of the outlet subcooling in upflow and downflow on the CHF was quantitatively investigated. As a result of this study, a new CHF scheme covering downflow, countercurrent flow, and upflow was established in the rectangular channels within the ranges of parameters investigated in this study. 17 refs., 10 figs., 1 tab.

• OSTI ID: 5898123
• Journal Information: Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States), Journal Name: Journal of Heat Transfer (Transactions of the ASME (American Society of Mechanical Engineers), Series C); (United States) Vol. 115:2; ISSN 0022-1481; ISSN JHTRAO
• Country of Publication: United States
• Language: English

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