Feasibility of Thulium-170, Produced on Site, for Radioisotope Power Generation

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Scientific paper

Thulium-170 has been suggested as a replacement for 238Pu jn some radioisotope power generation applications. The proposed approach is to activate 169Tm within the core or reflector of a stationary site power nuclear reactor at a Lunar or Mars outpost. The 170Tm so produced offers high theoretical power densities without the toxicity, availability, and nuclear launch problems of plutonium (only stable 169Tm would be launched). We examined issues raised by previous studies. It would be desirable to activate the thulia repeatedly. The ORIGEN2 code was used to model repeated irradiation/decay of thulium sesquioxide. We found no substantial buildup of neutron absorbing activation products that would prohibit repeated irradiation of the sample. Throughout the life of the sample, the dominant activity was the 170Tm. There was no buildup of toxic substances. At end of life, the sample would be Class B waste. Another advantage of recycling is that, for the first several recyclings, recycled targets achieve the same power level as fresh ones, but with shorter activation periods (or higher power levels with the same activation periods). However, sufficient 170Tm could not be produced. Using neutron conservation arguments, we developed an absolute upper bound on l70Tm power production of 1/3 watt thermal per kilowatt thermal of reactor power. Realistic values are much lower. Thus, the envisioned application appears impractical, although limited uses for 170Tm power might be found.

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