Abstract:An accurate knowledge of hydro-dynamic behavior of a liquid film flow on nuclear fuel rods is indispensable for analysis of the CHF under postulated loss-of-coolantaccidents in boiling water reactors. Despite of this importance, the microscopic knowledge of liquid film flow in the rod bundle is still not enough for us to construct the physical model for CHF analysis. Especially flow near the spacer is very unstable and complicated, so it is very difficult to obtain its information experimentally.The objective … Show more
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