Gas-cooled reactor for space power systems

Computer Science – Performance

Scientific paper

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Gas Cooled Reactors, Reactor Design, Reactor Safety, Reactor Technology, Space Power Reactors, Spacecraft Power Supplies, Brayton Cycle, Computer Techniques, Reaction Kinetics, Reactor Materials, Spacecraft Radiators

Scientific paper

Reactor characteristics based on extensive development work on the 500 MWt reactor for the Pluto nuclear ramjet are described for space power systems useful in the range of 2 to 20 MWe for operating time of 1 yr. The modest pressure drop through the prismatic ceramic core is supported at the outlet end by a ceramic dome which also serves as a neutron reflector. Three core materials are considered which are useful at temperatures up to about 2000 K. Most of the calculations are based on a beryllium oxide with uranium dioxide core. Reactor control is accomplished by use of a burnable poison, a variable leakage reflector, and internal control rods. Reactivity swings of 20 percent are obtained with 12 internal boron-10 rods for the size cores studied. Criticality calculations were performed using the ALICE Monte Carlo code. The inherent high temperature capability of the reactor design removes the reactor as a limiting condition on system performance. The low fuel inventories required, particularly for beryllium oxide reactors, make space power systems based on gas cooled near thermal reactors a lesser safeguard risk than those based on fast reactors.

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