Control rod drive mechanism with heat pipe cooling

Patent metadata

Field	Value
Publication number	US-11355252-B2
Application number	US-201816229554-A
Country	US
Kind code	B2
Filing date	Dec 21, 2018
Priority date	Dec 30, 2016
Publication date	Jun 7, 2022
Grant date	Jun 7, 2022

Abstract

A representative cooling system for a nuclear reactor control rod drive mechanism (CRDM) includes an evaporation section located within or next to the CRDM and a condensation section fluidly coupled to the evaporation section. The cooling system includes a set of heat fins coupled to drive coils in the CRDM and heat pipes that extend through the drive coils and heat fins. A fluid evaporates while in the evaporation section of the heat pipes from heat generated by the CRDM and moves out of the evaporation section into the condensation section in the heat fins. The fluid cools and condensates while in the condensation section, recirculating back into the evaporation section. This passive natural circulation cooling system reduces or eliminates the number of water hoses, piping, and other water pumping equipment typically used for cooling a CRDM thereby increasing nuclear reactor reliability and simplifying nuclear reactor operation and maintenance.

First claim

The invention claimed is:

1. A nuclear reactor system, comprising:
a control rod drive mechanism (CRDM) including a plurality of drive coils extending about an axis; and
a cooling system including:
a plurality of heat fins coupled to the drive coils;
an evaporation section positioned within an inner portion of the drive coils and the heat fins;
a condensation section positioned within an outer portion of the drive coils and the heat fins, wherein the outer portion is positioned farther radially from the axis than the inner portion; and
a fluid configured to:
evaporate while in the evaporation section from heat absorbed from the CRDM and flow out of the evaporation section into the condensation section, and
condense while in the condensation section after moving away from the CRDM and recirculate back into the evaporation section.

2. The nuclear reactor system of claim 1 , further comprising a plurality of disconnect coils configured to electromagnetically retain a disconnect magnet in the CRDM, wherein the heat fins extend around the disconnect coils.

3. The nuclear reactor system of claim 1 , wherein the drive coils and the heat fins form an elongated annular shape around an annular drive shaft housing of the CRDM.

4. The nuclear reactor system of claim 1 , wherein the cooling system includes a plurality of heat pipes that extend in loops through the drive coils and the heat fins, wherein the heat pipes define the evaporation section and the condensation section, and wherein the heat pipes contain the fluid.

5. The nuclear reactor system of claim 4 , wherein the cooling system further includes insulation formed around inner portions of the heat pipes located in the heat fins.

6. The nuclear reactor system of claim 5 , wherein the cooling system further includes condensation channels formed around outer portions of the heat pipes located in the heat fins.

7. The nuclear reactor system of claim 4 , further comprising a vessel positioned to house the CRDM and a nuclear reactor, wherein the heat pipes extend from the CRDM to an inside surface of the vessel.

8. The nuclear reactor system of claim 1 wherein:
the drive coils are located around an outside surface of a drive shaft housing;
the CRDM includes:
drive magnets located around an inside surface of the drive shaft housing;
a drive shaft connected toward a top end to the drive magnets and connected toward a bottom end to a nuclear control rod assembly; and

the drive coils are positioned to receive electrical energy and to lift the drive magnets to raise the drive shaft and the nuclear control rod assembly, and wherein the cooling system is positioned to remove heat from the drive coils while the drive coils lift the drive shaft and the nuclear control rod assembly.

9. A nuclear reactor system, comprising:
a control rod drive mechanism (CRDM) including a plurality of drive coils; and
a cooling system including:
a heat fin coupled to the drive coils;
an evaporation section positioned within at least a portion of the drive coils;
a condensation section fluidly coupled to the evaporation section and positioned within a portion of the heat fin; and
a fluid configured to:
evaporate while in the evaporation section from heat absorbed from the CRDM and flow out of the evaporation section into the condensation section, and
condense while in the condensation section after moving away from the CRDM and recirculate back into the evaporation section.

10. The nuclear reactor system of claim 9 , wherein the drive coils are positioned about an axis, wherein the cooling system includes a heat pipe extending in a loop, wherein the evaporation section is an inner portion of the loop, and wherein the condensation section is an outer portion of the loop positioned farther from the axis than the inner portion.

11. The nuclear reactor system of claim 9 , wherein the drive coils are positioned about an axis, wherein the cooling system includes a plurality of heat pipes circumferentially spaced around the axis, wherein a first portion of the heat pipes defines the evaporation section, and wherein a second portion of the heat pipes defines the condensation section.

12. The nuclear reactor system of claim 11 , wherein the heat pipes each extend in a loop, wherein the first portion of the heat pipes includes an inner portion of each of the loops, wherein the second portion of the heat pipes includes an outer portion of each of the loops, and wherein the outer portions are positioned farther from the axis than the inner portions.

13. The nuclear reactor system of claim 9 , wherein the CRDM further includes a drive shaft coupled to a control rod assembly, and wherein the drive coils are operable to raise and lower the drive shaft.

Assignees

• Nuscale Power Llc

Inventors

• Lobscheid Christian
• Noel Derek

Classifications

• H02K9/225

  Heat pipes · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C7/14 Primary

  Mechanical drive arrangements · CPC title

• G21C7/18

  Means for obtaining differential movement of control elements · CPC title

• G21C15/257

  using heat-pipes {(in general F28D, F28F)} · CPC title