A Blowdown Critical Heat Flux Experimental Vehicle

Abstract

In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature, and ultimately, fuel failure. It has not yet been determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due to a loss-of-coolant accident. There are limited comprehensive experiments at prototypic conditions. To address this deficiency, a quality separate-effects test facility was built to simulate an electrically heated rod under blowdown conditions. Testing reached full pressurized water reactor thermal-hydraulic conditions. With scaled break sizes as large as a double-end cold leg break, CHF was repeatedly measured with depressurization rates ranging from 7 to 17 MPa s−1. These measurements at prototypic conditions acquired in a controlled methodology are novel to the body of knowledge. Several steady-state CHF methods and heater models were evaluated using RELAP5-3D simulations and the Dakota framework. The results showed that many steady-state CHF methods performed inadequately, but that recently developed wide-ranged, look-up table methods had the most acceptable results. Additionally, the results showed no significant correlation between prediction accuracy and the depressurization rates tested.