Subcooled Liquid Flow Research Articles

Analytical solution for the transient thermal response of volumetrically heated fixed porous nuclear debris beds

An analytical solution is presented for the problem of the transient distribution of fluid and solid temperatures in a volumetrically heated fixed porous nuclear debris bed through which a single-phase fluid, either subcooled liquid or superheated vapor, is flowing. The one-dimensional, time-dependent Modified Dispersion-Concentric Model (D-C Model) is used in the analysis of this problem. The method of solution is based on transformations that reduce the equations and then the application of Green's function in a straightforward manner. The mathematical solution characteristics for the transient fluid and solid temperature distributions are analyzed for subcooled liquid flow and for superheated vapor flow. Also, the transient fluid and solid phase temperature distributions for infinite time are compared with steady-state experimental data.

A semi-empirical theory for forced-flow turbulent film boiling of subcooled liquid along a horizontal plate

Based on a previous study [1], aphysical model is proposed in this paper to analyze the film boiling heat transfer for turbulent flow of subcooled liquid along a horizontal plate. The corresponding mathematical descriptions are given in detail and an analytical expression has been obtained as equation (28), which is simple in form. The empirical values of coefficient k and exponent m are determined from experiments with subcooled water. As a result, equation (30) will be adaptable for practical use in engineering analysis of high-temperature quenching process for rolled metals.

Critical Heat Fluxes and Flow Patterns in High-Pressure Boiling Water Flows

High-speed motion pictures (4300 pictures/sec) of boiling water flow patterns in conditions of forced flow at 1000 psia pressure in a vertical heated rectangular channel were taken over the range of mass velocities from 50 to 400 lb/sec-ft2, fluid states from bulk subcooled liquid flow to bulk boiling flow at 0.66 steam quality, and heat fluxes up to and including the critical heat flux level. Eighty critical heat flux determinations were made in the course of the experiment at 1000 psia in conditions of bulk boiling. The motion pictures provide photographic evidence of the general arrangement of the flow in conditions of bulk boiling at high pressure with heat fluxes near and including the critical heat flux level.