Article ID Journal Published Year Pages File Type
6762026 Nuclear Engineering and Design 2014 8 Pages PDF
Abstract
The critical heat flux (CHF) in the vicinity of an inclination angle of 90° for the reactor vessel lower head external wall was measured on a downward facing curved surface. Two test sections having radii of curvature 0.15 m and 0.5 m were used. The objective was to investigate the effect of heater material and the combined effect of the heater material and additives on flow boiling CHF to assess the CHF enhancement under accident conditions. The heater material SA508 (low alloy steel) and the additive solutions of boric acid and tri-sodium phosphate (TSP, Na3PO4·12H2O) were used. An enhancement of CHF with the SA508 heater was confirmed in comparison with stainless steel reference heaters, which have negligible steel oxidation. As a result of the combined effect tests, the CHF with a TSP solution was reduced and the CHFs with a boric acid and a mixed solution (boric acid and TSP) were enhanced in comparison with the deionized water reference case. The CHF results are discussed in terms of steel oxidation according to the pH of the working fluid. Steel oxidation is also affected by local flow conditions as shown in the R = 0.5 m tests in which the boric acid and mixed solution had negligible effects on CHF enhancement. Under a relatively high concentration of boric acid (2.5 wt%), additive deposition as well as steel oxidation were observed and resulted in CHF enhancement.
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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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