Patent Number: 
Section: claims

1. A method, comprising:receiving at least one first reactor core parameter distribution associated with a state of a first core of a reference nuclear reactor;generating an initial fuel loading distribution for a simulated beginning-of-cycle (BOC) core of a nuclear reactor, wherein the BOC core of the nuclear reactor includes a plurality of simulated fuel assemblies;selecting an initial set of positions associated with a set of regions within the simulated BOC core;generating an initial set of fuel design parameter values utilizing at least one design variable of at least one of the set of regions;calculating at least one second reactor core parameter distribution of the simulated BOC core utilizing the initial set of fuel design parameter values associated with the set of regions located at the initial set of positions; andgenerating, by a controller, a loading distribution by performing at least one perturbation process on the set of regions located at the initial set of positions in order to determine a subsequent set of positions for the set of regions of the simulated BOC core; andarranging, by a fuel handler communicatively coupled to the controller, at least one fuel assembly of a second core of the nuclear reactor according to the subsequent set of positions. 2. The method of claim 1, wherein the state of the first core of the reference nuclear reactor includes an equilibrium state of the first core of the reference nuclear reactor. 3. The method of claim 1, wherein the reference nuclear reactor includes at least one of a reference thermal nuclear reactor, a reference fast nuclear reactor, a reference breed-and-burn nuclear reactor, or a reference traveling wave reactor. 4. The method of claim 1, wherein the at least one first reactor core parameter distributionincludes at least one of a power density distribution, a rate of change of the power density distribution, a reactivity distribution, or a rate of change of the reactivity distribution. 5. The method of claim 1, wherein the first core of the reference nuclear reactor includes at least one reference fuel assembly. 6. The method of claim 1, wherein at least a portion of the BOC core includes at least one of simulated recycled nuclear fuel, simulated unburned nuclear fuel, or simulated enriched nuclear fuel. 7. The method of claim 1, wherein the simulated BOC core includes a simulated beginning-of-life (BOL) core of the nuclear reactor. 8. The method of claim 1, wherein at least one of the initial set of positions corresponds to one of the set of regions. 9. The method of claim 8, wherein at least one of the set of regions encompasses at least one simulated fuel assembly. 10. The method of claim 8, wherein the at least one of the set of regions is a three-dimensional region corresponding to at least one of a selected volume, a selected shape, or a selected number of the set of regions. 11. The method of claim 1, wherein at least one of the initial set of fuel design parameter values is associated with one of the set of regions, andwherein generating the initial set of fuel design parameter values includes utilizing a thermodynamic variable of the at least one of the set of regions. 12. The method of claim 1, wherein at least one of the fuel design parameter values is associated with one of the set of regions, andwherein generating the initial set of fuel design parameter values includes utilizing a neutronic parameter of the at least one of the set of regions. 13. The method of claim 12, wherein generating the initial set of fuel design parameter values utilizing the neutronic parameter of the at least one of the set of regions includes utilizing a k-infinity value of the at least one of the set of regions. 14. The method of claim 1, wherein generating the initial set of fuel design parameter valuesincludes generating an initial set of enrichment values utilizing the at least one design variable. 15. The method of claim 1, wherein generating the initial set of fuel design parameter valuesincludes generating an initial set of pin dimension values associated with a set of pins of a simulated fuel assembly of the simulated BOC core utilizing the at least one design variable. 16. The method of claim 15, wherein generating the initial set of pin dimension valuesincludes generating at least one of an initial set of pin configuration values, an initial set of pin geometry values, or an initial set of pin composition values associated with the set of pins of the simulated fuel assembly utilizing the at least one design variable. 17. The method of claim 1, wherein the at least one design variable corresponds to at least one of a set of pins of the set of regions, wherein at least one of the initial set of fuel design parameter values is associated with one of the set of regions. 18. The method of claim 17, wherein the at least one of the initial set of fuel design parameter values is associated with one of the set of pins. 19. The method of claim 1, wherein calculating the at least one second reactor core parameter distributionincludes calculating at least one of a power density distribution, a rate of change of the power density distribution, a reactivity distribution, or a rate of change of the reactivity distribution of the simulated BOC core by utilizing the initial set of fuel design parameter values. 20. The method of claim 1, wherein the subsequent set of positions define the loading distribution for the simulated BOC core. 21. The method of claim 1, wherein the subsequent set of positions reduce a deviation metric between the at least one second reactor core parameter distribution and the at least one first reactor core parameter distribution below a selected tolerance level. 22. The method of claim 1, wherein arranging the at least one fuel assembly is performed in response to generating the loading distribution. 23. The method of claim 1, wherein the nuclear reactor includes at least one of a thermal nuclear reactor, a fast nuclear reactor, a breed-and-burn nuclear reactor, or a traveling wave nuclear reactor. 24. The method of claim 1, wherein arranging the at least one fuel assemblyincludes translating, by the fuel handler, the at least one fuel assembly from an initial location to a subsequent location according to the subsequent set of positions. 25. The method of claim 1, wherein arranging the at least one fuel assemblyincludes replacing, by the fuel handler, the at least one fuel assembly according to the subsequent set of positions. 26. A non-transitory computer-readable medium comprising program instructions, wherein the program instructions are executable to:receive at least one first reactor core parameter distribution associated with a state of a first core of a reference nuclear reactor;generate an initial fuel loading distribution for a simulated beginning-of-cycle (BOC) core of a nuclear reactor, the simulated BOC core of the nuclear reactor containing a plurality of simulated fuel assemblies:select an initial set of positions associated with a set of regions within the simulated BOC core;generate an initial set of fuel design parameter values utilizing at least one design variable of at least one of the set of regions;calculate at least one second reactor core parameter distribution of the simulated BOC core utilizing the initial set of fuel design parameter values associated with the set of regions located at the initial set of positions of the simulated BOC core;generate a subsequent loading distribution by performing at least one perturbation process on the set of regions located at the initial set of positions in order to determine a subsequent set of positions for the set of regions; andcontrol a fuel handler to arrange at least one fuel assembly of a second core of the nuclear reactor according to the subsequent set of positions. 27. The non-transitory computer-readable medium of claim 26, wherein the at least one first reactor core parameter distribution is associated with an equilibrium state of the first core of the reference nuclear reactor. 28. The non-transitory computer-readable medium of claim 26, wherein the reference nuclear reactor includes at least one of a reference thermal nuclear reactor, a reference fast nuclear reactor, a reference breed-and-burn nuclear reactor, or a reference traveling wave reactor. 29. The non-transitory computer-readable medium of claim 26, wherein the at least one first reactor core parameter distributionincludes at least one of a power density distribution, a rate of change of the power density distribution, a reactivity distribution, or a rate of change of the reactivity distribution. 30. The non-transitory computer-readable medium of claim 26, wherein at least a portion of the simulated BOC core includes at least one of simulated recycled nuclear fuel, simulated unburned nuclear fuel, or simulated enriched nuclear fuel. 31. The non-transitory computer-readable medium of claim 26, wherein causing the fuel handler to arrange the at least one fuel assembly is in response to generating the loading distribution determination. 32. The non-transitory computer-readable medium of claim 26, wherein the simulated BOC core includes a simulated beginning-of-life (BOL) core of the nuclear reactor. 33. The non-transitory computer-readable medium of claim 26, wherein at least one of the set of regions encompasses at least one simulated fuel assembly. 34. A nuclear reactor system comprising:a controller configured to:receive at least one first reactor core parameter distribution associated with a state of a core of a reference nuclear reactor;generate an initial fuel loading distribution for a simulated beginning-of-cycle (BOC) core of a nuclear reactor;select an initial set of positions associated with a set of regions within the simulated BOC core, at least one of the initial set of positions corresponding to one of the set of regions;generate an initial set of fuel design parameter values utilizing at least one design variable of at least one of the set of regions, wherein the at least one of the initial set of fuel design parameter values is associated with one of the set of regions of the simulated BOC core;calculate at least one second reactor core parameter distribution of the simulated BOC core utilizing the initial set of fuel design parameter values associated with the set of regions located at the initial set of positions; andgenerate a subsequent loading distribution by performing at least one perturbation process on the set of regions located at the initial set of positions in order to determine a subsequent set of positions for the set of regions, the subsequent set of positions defining the loading distribution for the simulated BOC core, wherein the subsequent set of positions reduce the difference between the at least one first reactor core parameter distribution and the at least one second reactor core parameter distribution below a selected tolerance level;the nuclear reactor, the nuclear reactor including a nuclear reactor core including a plurality of fuel assemblies; anda fuel handler configured to arrange at least one of the plurality of fuel assemblies according to the subsequent loading distribution determined by the controller. 35. The nuclear reactor system of claim 34, wherein the at least one first reactor core parameter distribution is associated with an equilibrium state of the core of the reference nuclear reactor. 36. The nuclear reactor system of claim 34, wherein the reference nuclear reactor includes at least one of a reference thermal nuclear reactor, a reference fast nuclear reactor, a reference breed-and-burn nuclear reactor, or a reference traveling wave reactor. 37. The nuclear reactor system of claim 34, wherein the at least one first reactor core parameter distributionincludes at least one of a power density distribution, a rate of change of the power density distribution, a reactivity distribution, or a rate of change of the reactivity distribution. 38. The nuclear reactor system of claim 34, wherein at least a portion of the simulated BOC core includes at least one of simulated recycled nuclear fuel, simulated unburned nuclear fuel, or simulated enriched nuclear fuel. 39. The nuclear reactor system of claim 34, wherein the simulated BOC core includes a plurality of simulated fuel assemblies. 40. The nuclear reactor system of claim 34, wherein the at least one of the initial set of positions corresponds to one of the set of regions. 41. The nuclear reactor system of claim 34, wherein generating the initial set of fuel design parameter valuesincludes utilizing a thermodynamic variable of the at least one of the set of regions. 42. The nuclear reactor system of claim 34, wherein generating the initial set of fuel design parameter valuesincludes utilizing a neutronic parameter of the at least one of the set of regions. 43. The nuclear reactor system of claim 34, wherein calculating the at least one second reactor core parameter distributionincludes calculating at least one of a power density distribution, a rate of change of the power density distribution, a reactivity distribution, or a rate of change of the reactivity distribution of the simulated BOC core. 44. The nuclear reactor system of claim 34, wherein the subsequent set of positions define the loading distribution for the simulated BOC core. 45. The nuclear reactor system of claim 34, wherein the fuel handler is communicatively coupled to the controller and is configured to arrange the at least one of the plurality of fuel assemblies in response to the controller generating the subsequent loading distribution. 46. The nuclear reactor system of claim 34, wherein the fuel handler is communicatively coupled to the controller and is configured to arrange the at least one of the plurality of fuel assemblies in response to a signal from a user input device. 47. The nuclear reactor system of claim 34, wherein the nuclear reactor includes at least one of a thermal nuclear reactor, a fast nuclear reactor, a breed-and-burn nuclear reactor, or a traveling waver nuclear reactor. 48. The nuclear reactor system of claim 34, wherein the fuel handler is configured to translate the at least one of the plurality of fuel assemblies from an initial location to a subsequent location according to the subsequent set of positions. 49. The nuclear reactor system of claim 34, wherein the fuel handler is configured to replace the at least one of the plurality of fuel assemblies according to the subsequent set of positions.