Control rod damping system

Patent metadata

Field	Value
Publication number	US-11024433-B2
Application number	US-201715858073-A
Country	US
Kind code	B2
Filing date	Dec 29, 2017
Priority date	Dec 30, 2016
Publication date	Jun 1, 2021
Grant date	Jun 1, 2021

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.

First claim

The invention claimed is:

1. A control rod for inserting into a guide tube of a nuclear reactor fuel assembly of a nuclear reactor module, comprising:
a first section including an active material for inserting into the guide tube and controlling a fission rate in a nuclear reactor core, the first section having a first outside diameter;
a second section configured to attach to a head assembly of the nuclear reactor module;
a dampening section located between the first section and the second section, wherein the dampening section has a second outside diameter larger than the first outside diameter such that, the dampening section reduces a separation distance between an outside surface of the control rod and an inside surface of the guide tube to decelerate the control rod when entering a top end of the guide tube; and
a spring positioned inside the dampening section between the first section and the second section.

2. The control rod of claim 1 , further comprising a cylindrical cladding including:
a bottom portion at least partially defining the first section and retaining the active material, wherein the bottom portion has a first wall thickness; and
a top portion at least partially defining the dampening section and having a second continuously increasing wall thickness.

3. The control rod of claim 2 , wherein the spring is located in the top portion of the cladding above the active material.

4. The control rod of claim 1 , wherein the second section has a third outside diameter, and wherein the second outside diameter of the dampening area continuously increases along the dampening section from the first outside diameter of the first section to the third outside diameter of the second section.

5. The control rod of claim 1 , wherein the first section is shaped and sized to extend down to a bottom end of the guide tube when the dampening section enters a top end of the guide tube.

6. The control rod of claim 1 , wherein the dampening section is shaped and sized to maintain a reduced separation distance when fully inserted into the top end of the guide tube.

Assignees

• Nuscale Power Llc

Inventors

• Snuggerud Ross Douglas

Classifications

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C9/02

  Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; {Control elements having arrangements activated in an emergency}(control elements per se G21C7/00) · CPC title

• G21C7/117

  Clusters of control rods; Spider construction · CPC title

• G21C3/322

  Means to influence the coolant flow through or around the bundles · CPC title

• G21C3/3315

  Upper nozzle · CPC title