Control rod damping system
AssigneeNuScale Power, LLC
InventorRoss Douglas Snuggerud
Life of this patent
Estimating the term…
Abstract
A damping area or “dash pot” on the upper ends of control rods absorb energy from dropped control rod assemblies without narrowing the diameter of guide tubes. As a result, coolant can freely flow through the guide tubes reducing boiling water issues. The dampening area reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tubes decelerating the control rods when entering a top end of the guide tubes. In another example, the dampening area may be located on a drive shaft. The dampening area may have a larger diameter than an opening in a drive shaft support member that decelerates the drive shaft when dropped by a drive mechanism.
Claims17
A control rod for inserting into a guide tube of a nuclear reactor fuel assembly, comprising:
- an upper plug;
- cladding coupled to the upper plug, wherein the cladding comprises a continuous wall defining—
- an intermediate section extending from the upper plug, wherein the intermediate section includes a damping region having an upper damping location and a lower damping location farther from the upper plug than the upper damping location, and wherein a diameter of the damping region decreases from a first diameter at the upper damping location to a second diameter at the lower damping location;
- and
- a lower section extending downward from the damping region of the intermediate section;
- a neutron-absorbing material positioned in the lower section;
- and
- a spring extending through the intermediate section from the upper plug to the neutron-absorbing material.
A control rod for inserting into a guide tube of a nuclear reactor fuel assembly, comprising:
- an upper plug;
- cladding coupled to the upper plug, wherein the cladding comprises a continuous wall defining—
- an intermediate section extending from the upper plug, wherein the intermediate section includes a damping region having an upper damping location and a lower damping location farther from the upper plug than the upper damping location, wherein diameter of the damping region decreases from a first diameter at the upper damping location to a second diameter at the lower damping location, and wherein the damping region is configured to be positioned above the guide tube during normal operation of the nuclear reactor fuel assembly and to enter the guide tube only during a SCRAM operation of the nuclear reactor fuel assembly;
- and
- a lower section extending downward from the damping region of the intermediate region;
- a neutron-absorbing material positioned in the lower section;
- and
- a spring extending through the intermediate section from the upper plug to the neutron-absorbing material.
A nuclear reactor system, comprising:
- a nuclear core;
- a guide tube extending at least partially into the nuclear core;
- a control rod including—
- an upper plug;
- cladding coupled to the upper plug, wherein the cladding comprises a continuous wall defining—
- an intermediate section extending from the upper plug, wherein the intermediate section includes a damping region having an upper damping location and a lower damping location farther from the upper plug than the upper damping location, and wherein diameter of the damping region decreases from a first diameter at the upper damping location to a second diameter at the lower damping location;
- a lower section extending downward from the damping region of the intermediate section;
- an active material positioned in the lower section and configured to control a fission rate of the nuclear core;
- and
- a spring extending through the intermediate section from the upper plug to the neutron-absorbing material;
- and
- a control rod drive mechanism (CRDM) coupled to the control rod and configured to move the control rod relative to the guide tube such that the damping region is positioned above the guide tube during normal operation of the nuclear reactor system and enters the guide tube only during a SCRAM operation of the nuclear reactor system.
Dependencies are inferred from the claim text.