AbstractThe critical heat flux (CHF) of subcooled flow boiling for water was experimentally investigated as a fundamental study on high-heat-flux cooling of fusion reactor components. A circular tube with 3 mm inside diameter was heated directly by Joule heating. The experiments were conducted in the pressure range 0.3–1.0 MPa under uniform heating conditions. It was verified that the modified Tong correlation, whivh was proposed by the authors, predicts the accurate CHF of lower than about 20 MW/m2 in the pressure range from 0.1 to 13.8 MPa and was also useful in the prediction of the high CHF from 20 to 130 MW/m2 at low and medium pressures, which might correspond to the cooling conditions of fusion reactor components. The high-CHF data were compared with the Gunther, the Gambill-Greene and the Weisman-Pei correlation and the effects of the experimental parameters on the CHF-pressure relation were discussed. The flow conditions of the cooling water at which a CHF from 10 to 40 MW/m2 might be achieved, were examined using the modified Tong correlation.
Thermal hydraulic assessment on the full banana model of COOL blanket for CFETR