広い圧力範囲の強制流動サブクール沸騰・限界熱流束の予測

概要

論文の詳細を見る
As for the critical heat flux (CHF) of subcooled water flow boiling, the existing data have so far been limited within a comparatively high-pressure regime, i. d., from 2.5 to 20.0 MPa. However, under the necessity of high heat removal from fusion reactor components, a few experiments have recently been carried out under low pressures, providing some reliable data for 0.1 to 2.5 MPa. Corresponding to this situation, this paper reports on the result of all attempt to extend the applicable range of the author's previous model of CHF up to the foregoing low-pressure regime. The extension is made successfully, and the model is endowed with the ability to predict CHF with nearly the same accuracy over a wide pressure range of 0.1 to 20.0 MPa.
一般社団法人日本機械学会の論文
1991-10-25