Two Dimensional Analysis of Conduction-Controlled Rewetting with Internal Heat Generation

Abstract

An exact solution of the quasi-steady two dimensional conduction equation for the rewetting of a nuclear fuel rod and a tube with internal heat generation in water reactor core cooling is obtained. The analysis adopts the conventional model of two heat transfer regions: one where the coolant wets the fuel rod with a high heat transfer coefficient, hw and the other ahead of the quench front with a much lower heat transfer coefficient, hd, (10^-3 to 10^-5 of hw), the steam surrounds the rod or clad is assumed superheatedwand is computed. Under these conditions, the wet front velocity and the temperature distribution versas internal heat generation in the rod and in the thin tube are computed. The present solution covers all ranges of Biot number, but the calculations are performed from 10^-2 to 10^2 of Biot number, dimensionless Leidenfrost temperature from zero to 1, and dimensionaless heat generation from zero to 10^-3.