A Coaxial Flow Reactor - A Gaseous Nuclear-Rocket Concept

Herbert Weinstein; Robert G Ragsdale

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NASA NTRS · 19630042704

A Coaxial Flow Reactor - A Gaseous Nuclear-Rocket Concept

Herbert Weinstein·Robert G Ragsdale

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Abstract

Aspects of a new gaseous nuclear-rocket concept are considered. The principle of this type of cavity reactor is one of maintaining the separation of two coaxial streams - fuel within propellant - rather than attaining the separation of fuel propellant gases within the cavity. An acceptably low uranium consumption rate is possible if the fuel stream can be maintained at an axial velocity which is 1/100 to 1/1000 of the propellant velocity. An elementary hydrodynamic analysis for laminar incompressible flow indicates that the average uranium core velocity may only reach 2 to 11 times the initial core velocity for a typical reactor. The results of a 1-D criticality analysis for a D2O/(235)U system show that the effect of shrinking the fuel region within the reactor cavity is not serious; the effects of moderator heating and structural materials on critical mass are also shown. Overall rocket performance calculations are made for reasonable operating conditions; these results indicate that thrusts from 25,000 to 50,000 pounds and accelerations from 10(exp -1) to 3 g are possible.

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Herbert Weinstein, Robert G Ragsdale. 1960-12-05. A Coaxial Flow Reactor - A Gaseous Nuclear-Rocket Concept. https://ntrs.nasa.gov/citations/19630042704

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