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AIP Conference Proceedings
A thermal-hydraulic model of an open-cycle gas core nuclear rocket is used to examine the fuel containment characteristics of the system. A parametric analysis is performed which studies how the average containment time, average number density, and mass loading of the fuel vary as a function of several design and operational parameters. The containing effect of the injected fluids is studied by varying the velocity and injection angle of the outer wall flow. The effect of rocket acceleration ondoi:10.1063/1.2950157 fatcat:zhlfoynci5glbgfhd3zwqbacyi