Turbulent Flow in a Nuclear Heat-Exchanger

Author: Hemmingway, Richard Earl

Year: 1959

Degree: Engineer's thesis

Advisor: Rannie, W. Duncan

Committee Member: Unknown, Unknown

Option: Aeronautics

DOI: 10.7907/0QX0-8Y04

Abstract

A gas-cooled, cylindrical, nuclear reactor is used as the basis in the theoretical derivation of the coolant's enthalpy increase and pressure loss across the reactor. Turbulent flow is assumed in the coolant passages of the reactor, and the Reynolds analogy is used as the basis for correlating the heat transfer coefficient and the friction coefficient.

The general equations are derived and two examples, a nuclear-hydrogen rocket and a ramjet, are given to demonstrate applications of the general results.

Files

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