A prediction model of subcooled water flow boiling CHF for pressure in the range 0.1–20 MPa

Abstract Existing data for the critical heat flux (CHF) of subcooled water flow boiling have so far been limited within a comparatively high pressure regime, say, from 2.5 to 20.0 MPa. However, under the necessity of high flux removal of heat from fusion reactor components, some experiments have recently been made under low pressures, providing a tolerable number of reliable data for 0.1–2.5 MPa. Corresponding to this situation, this paper reports the result of an attempt of extending the applicable range of the author's previously presented model of subcooled flow boiling CHF to the low pressure regime. The extension is made preserving the structure of the model, and the model is endowed with the capability to predict CHF with nearly the same accuracy over a wide pressure range of 0.1–20.0 MPa.