A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM).

A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof includes a processor coupled to memory, the memory configuring the processor to execute a fuel element analysis and an output configured to communicate data that describes the thermo-mechanical performance of the fuel element and fuel design based on the fuel element performance analysis. The processor is configured to estimate the mechanical behavior of a fuel by creating separate variables for the open and closed porosity components, conducting a routine for the open and closed porosity components that processes the current state of the fuel and updates the current state and forces of each of the open and closed porosity components, and combining the updates for the current state and forces according to a weighting; and estimate the creep and swelling behavior of a cladding.

A computerized system for modeling reactor fuel element and fuel design to determine the thermo-mechanical performance thereof includes a processor coupled to memory, the memory configuring the processor to execute a fuel element analysis and an output configured to communicate data that describes the thermo-mechanical performance of the fuel element and fuel design based on the fuel element performance analysis. The processor is configured to estimate the mechanical behavior of a fuel by creating separate variables for the open and closed porosity components, conducting a routine for the open and closed porosity components that processes the current state of the fuel and updates the current state and forces of each of the open and closed porosity components, and combining the updates for the current state and forces according to a weighting; and estimate the creep and swelling behavior of a cladding.

A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The core has a low-enriched uranium loading strictly higher than 3.0 gU/cm.sup.3 and includes less than 10 wt % of aluminium phase and/or aluminium compounds other than UAl.sub.2 phase, than UAl.sub.3 phase, and than UAl.sub.4 phase. A corresponding nuclear fuel product is also provided.

A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The core has a low-enriched uranium loading strictly higher than 3.0 gU/cm.sup.3 and includes less than 10 wt % of aluminium phase and/or aluminium compounds other than UAl.sub.2 phase, than UAl.sub.3 phase, and than UAl.sub.4 phase. A corresponding nuclear fuel product is also provided.

A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminum and low-enriched uranium; and sealing said core in a cladding. The low-enriched uranium has a proportion of U235 below 20 wt %. The core includes more than 80 wt % of a mixture of UAl.sub.3 phase and UAl.sub.4 phase, and the mixture has a weight fraction of UAl.sub.3 phase higher than or equal to 50%, or the core includes more than 50 wt % of UAl.sub.2 phase. The core has a low-enriched uranium loading higher than 3.0 gU/cm.sup.3. The core includes less than 10 wt % in total of one or several material(s) taken from the list consisting of aluminum phase and aluminum compounds other than UAl.sub.2 phase, than UAl.sub.3 phase, and than UAl.sub.4 phase. A corresponding nuclear fuel product is also provided.

A method of producing a nuclear fuel product is provided. The method includes the steps of providing a core comprising aluminum and low-enriched uranium; and sealing said core in a cladding. The low-enriched uranium has a proportion of U235 below 20 wt %. The core includes more than 80 wt % of a mixture of UAl.sub.3 phase and UAl.sub.4 phase, and the mixture has a weight fraction of UAl.sub.3 phase higher than or equal to 50%, or the core includes more than 50 wt % of UAl.sub.2 phase. The core has a low-enriched uranium loading higher than 3.0 gU/cm.sup.3. The core includes less than 10 wt % in total of one or several material(s) taken from the list consisting of aluminum phase and aluminum compounds other than UAl.sub.2 phase, than UAl.sub.3 phase, and than UAl.sub.4 phase. A corresponding nuclear fuel product is also provided.

One embodiment provides a multi-segment rod that includes a plurality of rod segments. The rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials.

One embodiment provides a multi-segment rod that includes a plurality of rod segments. The rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials.