By United States. Dept. of Energy. Office of New Production Reactors
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In the tritium-production mode, the tritium targets would be sent to the on-site tritiumextraction facilities, where the tritium would be removed and contained. The tritium would then be shipped to SRS, where it would be purified and loaded into warhead reservoirs. The spent fuel would be transported to an on-site storage facility or a reprocessing facility, where enriched uranium and weapons-gn'ade plutonium might be recovered. Any enriched uranium not recycled to the fuel fabrication facility would be shipped to Oak Ridge to meet other reactor fuel requirements.
Materials for reactor fuel would be shipped to the site fuel-fabrication facility, where reactor fuel assemblies would be manufactured. Materials for targets would be shipped to the site target-fabrication facilities where tritium targets would be manufactured. • The Idaho Site possesses state-of-the-art reprocessing ,and wa_e management facilities that could reduce the cost of waste processing and high-level waste storage, The prefen'ed strategy provides for initial operations by a new production heavy water reactor at the Sava_mah River Site beginning around the year 2000.
Thus, there is greater uncertainty in the time and cost of LMR target development than for the other technology concepts. However, a number of promising target concepts exist, based partially on tests with other coolants. In the reference system presented for the LMR, the reactor operating temperature was reduced some 300°F from power reactor conditions to minimize target development uncertainties, A lithiurrgaluminum (LiA1) intermetallic alloy was identified as a reference target material for the LMSR.
New production reactors program plan by United States. Dept. of Energy. Office of New Production Reactors
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