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2 Spent Fuel Operations
Pages 7-12

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From page 7...
... ' The "direct transport" cadmium pool process for the Mark-IV involves dissolution of the uranium fuel in the anode basket into the molten salt (oxidation of uranium from the metal to U3+~. The U ions are then transported through the salt by forced convection to the cathode (steel mandrel)
From page 8...
... The cathode surfaces adjacent to the anode tubes are continuously scraped to remove the deposited uranium that falls into removable screen buckets positioned under the cathodes. The ACM to be tested in both the Mark-IV and Mark-V ERs has an outer diameter of just under 10 inches to be compatible with the 10-inch ports on the top of ER vessels and an anode batch capacity of about 37 kg.
From page 9...
... Therefore, experiments were conducted to determine the extent of co-dissolution of uranium and zirconium as well as the retention of noble metal fission products using a simulated fuel. Preliminary experiments resulted in achieving the goal of 98.5 percent removal of uranium from the anode basket to the cathode but fell short by S percent of retaining 80 percent of the zirconium in the anode basket.
From page 10...
... the selection of sodalite over zeolite as the host ceramic waste form for nonnoble fission products and transuranic elements (TRW) waste components from the molten processing salt of the EMT process and (2)
From page 11...
... Establishing the credibility of the EMT, as well as potential applications of EMT treatment to other types of DOE spent nuclear fuel, must eventually include resolution of waste form issues.


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