21 research outputs found
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Alloy Development Program. Quarterly technical progress letter, October, November, December 1976
Progress is reported in six chapters: swelling and creep, analytical studies (of irradiation effects), coolant compatibility (sodium), and status of EBR-II irradiation tests (one table). Materials studied include HT-9, 330 ss, Inconel 706, A-286, Nimonic PE16, Inconel 718, 310 ss, various developmental alloys, and 316 ss. Nickel ions as well as reactor irradiations were used in the studies of radiation effects. (212 figs., 54 tables). (DLC
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Treatment of high-level wastes from the IFR fuel cycle
The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described
The Long-run Properties of the Demand for M3 in South Africa
No abstract available