Abstract: A coating for protecting a Zirconium alloy based layer of a nuclear fuel rod cladding is provided. The coating comprises a primary layer. A microstructure of the primary layer is comprised of a number of grains and is randomized. The primary layer is configured with a density of about 94.5% or greater. A cladding for a nuclear fuel rod and a method for producing a cladding for a nuclear fuel rod are also provided.

Abstract: A method is described herein that produces UN from UF6 in at most two steps comprising UF6?intermediate?UN. The principle of the reaction is that in a first step, UF6 would be reduced to UxNy, where x may be an integer selected from 1 and 3, and y is an integer selected from 1 and 2. Reduction occurs at or near the surface of a gaseous membrane electrode where it is also in contact with a nitrogen bearing salt. In a second step, UxNy decomposes to UN and N2 gas, either in the same reactor as the first step or after removal to a separate unit for further processing.

Abstract: Annular nuclear fuel rods are disclosed. The annular nuclear fuel rods include an outer cladding tube made of ceramic composite or cermet composite, an inner cladding tube made of ceramic composite or cermet composite, a nuclear fuel region located between the outer cladding tube and inner cladding tube, and an open channel for liquid coolant to flow.

Abstract: A method is described herein that produces UN from UF6 in at most two steps comprising UF6?intermediate?UN. The principle of the reaction is that in a first step, UF6 would be reduced to UxNy, where x may be an integer selected from 1 and 3, and y is an integer selected from 1 and 2. Reduction occurs at or near the surface of a gaseous membrane electrode where it is also in contact with a nitrogen bearing salt. In a second step, UxNy decomposes to UN and N2 gas, either in the same reactor as the first step or after removal to a separate unit for further processing.

Abstract: Electrochemical cells and methods are described that can be utilized for the recovery of tritium directly from a molten lithium metal solution without the need for a separation or concentration step prior to the electrolytic recovery process. The methods and systems utilize an ion conducting electrolyte that conducts either lithium ion or tritide ion across the electrochemical cell.

Abstract: A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

Abstract: A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

Abstract: A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.

Abstract: Electrochemical cells and methods are described that can be utilized for the recovery of tritium directly from a molten lithium metal solution without the need for a separation or concentration step prior to the electrolytic recovery process. The methods and systems utilize an on conducting electrolyte that conducts either lithium ion or tritide ion across the electrochemical cell.

Abstract: A galvanic cell and methods of using the galvanic cell is described for the recovery of uranium from used nuclear fuel according to an electrofluorination process. The galvanic cell requires no input energy and can utilize relatively benign gaseous fluorinating agents. Uranium can be recovered from used nuclear fuel in the form of gaseous uranium compound such as uranium hexafluoride, which can then be converted to metallic uranium or UO2 and processed according to known methodology to form a useful product, e.g., fuel pellets for use in a commercial energy production system.