Transient Hydraulics and Heat Transfer in Turbulent Flow
Abstract
In a reactor transient analysis, the friction factor and the heat transfer coefficient are assumed equal to the steady-state values, even in a transient state. The transient turbulent flow in a circular tube subjected to a step change of presure gradient is calculated numerically. Transient variations of the friction factor and the heat transfer coefficient are obtained. Effects of the Reynolds number and a wall heat capacity are also examined. The quasi-static momentum equation is found to be approximately valid for both accelerated and decelerated turbulent flows. The quasi-static energy equation is valid for flow transients of gas-cooled reactors.
- Publication:
-
Nuclear Technology
- Pub Date:
- September 1976
- DOI:
- 10.13182/NT76-A31642
- Bibcode:
- 1976NucTe..30..246K
- Keywords:
-
- Friction Factor;
- Gas Cooled Reactors;
- Heat Transfer Coefficients;
- Hydraulics;
- Reactor Technology;
- Transient Response;
- Turbulent Flow;
- Nuclear Reactors;
- Numerical Analysis;
- Pressure Gradients;
- Steady State;
- Transient Heating;
- Wall Temperature;
- Fluid Mechanics and Heat Transfer