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Turbulent flow in a nuclear heat-exchanger

Hemmingway, Richard E. (1959) Turbulent flow in a nuclear heat-exchanger. Engineer's thesis, California Institute of Technology.


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.

Item Type:Thesis (Engineer's thesis)
Degree Grantor:California Institute of Technology
Major Option:Aeronautics
Thesis Committee:
  • Rannie, W. Duncan (chair)
Defense Date:1 January 1959
Record Number:etd-01092006-144119
Persistent URL:
Default Usage Policy:No commercial reproduction, distribution, display or performance rights in this work are provided.
ID Code:81
Deposited By: Imported from ETD-db
Deposited On:10 Jan 2006
Last Modified:25 Dec 2012 14:57

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