Patent classifications
G21C7/117
HIGH TEMPERATURE CONTROL RODS FOR LIGHT WATER REACTORS
A high temperature control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500? C. that does not form a eutectic with a melting point less than 1500? C., and may further include a cladding material having a melting point greater than 1500? C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd.sub.2O.sub.3, Ir, B.sub.4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.
ABSORBER ROD ASSEMBLY AND ABSORBER ROD FOR NUCLEAR REACTOR
An absorber cluster for a nuclear reactor includes at least a first absorber assembly (22) and a second absorber assembly (24). Each absorber assembly respectively comprises neutron absorbing elements (20). Absorber elements (20) of each of the first absorber assembly (22) and the second absorber assembly (24) are made from the same material or the same combination of materials selected from the group of neutron absorbing materials consisting of a first europium hafnate, a second europium hafnate, a first samarium hafnate, a second samarium hafnate, hafnium carbide and samarium hexaboride. The absorber elements (20) of the first absorber assembly (22) have a cross-sectional structure different to that of the absorber elements (20) of the second absorber assembly (24).
ABSORBER ROD ASSEMBLY AND ABSORBER ROD FOR NUCLEAR REACTOR
An absorber cluster for a nuclear reactor includes at least a first absorber assembly (22) and a second absorber assembly (24). Each absorber assembly respectively comprises neutron absorbing elements (20). Absorber elements (20) of each of the first absorber assembly (22) and the second absorber assembly (24) are made from the same material or the same combination of materials selected from the group of neutron absorbing materials consisting of a first europium hafnate, a second europium hafnate, a first samarium hafnate, a second samarium hafnate, hafnium carbide and samarium hexaboride. The absorber elements (20) of the first absorber assembly (22) have a cross-sectional structure different to that of the absorber elements (20) of the second absorber assembly (24).
NUCLEAR FUEL CORE AND METHODS OF FUELING AND/OR DEFUELING A NUCLEAR REACTOR, CONTROL ROD DRIVE SYSTEM FOR NUCLEAR REACTOR, SHUTDOWN SYSTEM FOR NUCLEAR STEAM SUPPLY SYSTEM, NUCLEAR REACTOR SHROUD, AND/OR LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM
Portable nuclear fuel cartridge comprising a unitary support structure and plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. Control rod drive system for a nuclear reactor. A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. A nuclear reactor including a cylindrical body having an internal cavity, nuclear fuel core, and a shroud disposed in the cavity. A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power.
NUCLEAR FUEL CORE AND METHODS OF FUELING AND/OR DEFUELING A NUCLEAR REACTOR, CONTROL ROD DRIVE SYSTEM FOR NUCLEAR REACTOR, SHUTDOWN SYSTEM FOR NUCLEAR STEAM SUPPLY SYSTEM, NUCLEAR REACTOR SHROUD, AND/OR LOSS-OF-COOLANT ACCIDENT REACTOR COOLING SYSTEM
Portable nuclear fuel cartridge comprising a unitary support structure and plurality of nuclear fuel assemblies that collectively form a nuclear fuel core. Control rod drive system for a nuclear reactor. A nuclear steam supply system having a shutdown system for removing residual decay heat generated by a nuclear fuel core. A nuclear reactor including a cylindrical body having an internal cavity, nuclear fuel core, and a shroud disposed in the cavity. A nuclear reactor cooling system with passive cooling capabilities operable during a loss-of-coolant accident (LOCA) without available electric power.
Control rod guide tube with an extended intermediate guide assembly
A nuclear reactor having an upper internals control rod assembly guide tube formed from upper and lower sections that are connected along a central axial region of the guide tube at an intermediate coupling. An extended control rod axial support is provided for at least some of the control rods over a finite distance within at least one of the interiors of the lower guide tube section or the upper guide tube section.
Control rod guide tube with an extended intermediate guide assembly
A nuclear reactor having an upper internals control rod assembly guide tube formed from upper and lower sections that are connected along a central axial region of the guide tube at an intermediate coupling. An extended control rod axial support is provided for at least some of the control rods over a finite distance within at least one of the interiors of the lower guide tube section or the upper guide tube section.
Control rod assembly impact limiter
A control rod assembly including at least one movable control rod including a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a terminal element engaged with a connecting rod of the CRDM and the at least one moveable control rod, and a kinetic energy absorbing element supported by the terminal element for absorbing kinetic energy during a SCRAM event, the kinetic energy absorbing element configured to act between the terminal element and an upper plate of an associated fuel assembly.
Control rod assembly impact limiter
A control rod assembly including at least one movable control rod including a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a terminal element engaged with a connecting rod of the CRDM and the at least one moveable control rod, and a kinetic energy absorbing element supported by the terminal element for absorbing kinetic energy during a SCRAM event, the kinetic energy absorbing element configured to act between the terminal element and an upper plate of an associated fuel assembly.
Extruded guide frame and manufacturing methods thereof
A control rod guide frame has a central passage of constant cross-section as a function of position along a central axis that passes through the central passage. The central passage is sized and shaped to guide a traveling assembly including at least one control rod as it moves along the central axis. The control rod guide frame comprises at least two radial guide frame sections secured around and defining the central passage. Each radial guide frame section may comprise an extruded radial guide frame section, which may be made of extruded steel. The central passage may include control rod guidance channels parallel the central axis and machined into the extruded radial guide frame sections. The at least two radial guide frame sections may be interchangeable. In some embodiments the at least two radial guide frame sections consist of between four and eight radial guide frame sections.