Accession Number:

AD0419313

Title:

A HEAT TRANSFER STUDY OF A NUCLEAR ROCKET REACTOR

Descriptive Note:

Master's thesis

Corporate Author:

AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OH

Personal Author(s):

Report Date:

1963-08-01

Pagination or Media Count:

78.0

Abstract:

A digital computer program was developed to investigate the coolant temperature and pressure and the material temperatures in a nuclear rocket reactor. The reactor uses hydrogen gas as the coolant and is operating steady-state conditions. The program is written in FORTRAN for execution on an IBM 7090 digital computer. Reactor geometry, input conditions of the coolant, power, power distribution, and reactor fuel thermal conductivity are variable input qualities. The hydrogen is treated as a perfect gas and the reactor is assumed to be perfectly insulated. The coolant and material temperatures are determined by an iterative technique. The transport properties of hydrogen are computed by empirical formulas which include the effect of both temperature and pressure. The FORTRAN source program, operating instructions, a sample problem and sample output data are included as appendices.

Subject Categories:

  • Nuclear Power Plants and Fission Reactor Engineering
  • Thermodynamics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE