Visualization of Supercritical Carbondioxide Pseudo-Boiling Inside a Rectangular Channel
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Abstract The characteristics of the supercritical fluids should be precisely investigated for the next generation nuclear power reactor, i.e., Super-critical water Cooled Reactor (SCR). There are few experiments for visual observation especially in forced convection, because of the difficulty of the experiment.
2014 ◽
Vol 72
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pp. 338-349
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1970 ◽
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2003 ◽
Vol 3
(3)
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pp. 445-454