Evacuated containment vessel for nuclear reactor

Patent metadata

Field	Value
Publication number	US-11594342-B2
Application number	US-201715835332-A
Country	US
Kind code	B2
Filing date	Dec 7, 2017
Priority date	Nov 15, 2007
Publication date	Feb 28, 2023
Grant date	Feb 28, 2023

Abstract

A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

First claim

The invention claimed is:

1. A power module assembly comprising:
a reactor vessel containing a reactor core submerged in coolant;
a containment vessel encapsulating the reactor core and forming a containment region outside of the reactor vessel, wherein the containment region is completely dry during a normal operation of the power module assembly;
a flow limiter positioned between the reactor vessel and the containment vessel, wherein the containment vessel is configured to receive at least a portion of the coolant from the reactor vessel through the flow limiter during an emergency operation of the power module assembly, wherein the containment vessel is configured to prohibit the portion of the coolant received from the reactor vessel from escaping out of the containment vessel, and wherein the flow limiter is configured to stop release of the portion of the coolant when a pressure in the containment region exceeds a threshold value; and
a one-way flow valve positioned between the reactor vessel and the containment vessel to
(a) permit at least some of the portion of the coolant received from the reactor vessel to return therethrough from the containment vessel back into the reactor vessel and
(b) inhibit the coolant from flowing therethrough from the reactor vessel to the containment vessel.

2. The power module assembly of claim 1 , further comprising a pump to maintain the containment region in at least a partial vacuum.

3. The power module assembly of claim 2 , wherein the pump maintains the containment region at below atmospheric pressure.

4. The power module assembly of claim 1 , wherein the containment region is evacuated of gases during normal operation of the power module assembly to reduce convective heat transfer between the reactor core and the reactor vessel.

5. The power module assembly of claim 1 , wherein the flow limiter is configured to release the portion of the coolant in vapor form from the reactor vessel and into the containment vessel during the emergency operation, and wherein the emergency operation includes overheating of the reactor core.

6. The power module assembly of claim 5 , wherein the flow valve is positioned to allow at least some of the portion of the coolant received from the reactor vessel to flow back into the reactor vessel from the containment vessel once a steady state condition is reached between a level of the coolant in the reactor vessel and a level of the coolant in the containment vessel.

7. The power module assembly of claim 1 , wherein the emergency operation is a pressure event, wherein the flow limiter is configured to release the portion of the coolant into the containment region in response to the pressure event, and wherein the containment region remains substantially dry during normal operation of the power module assembly prior to the pressure event.

8. The power module assembly of claim 7 , wherein the portion of the coolant fills the containment region after the emergency operation.

9. The power module assembly of claim 1 , further comprising a reflective insulation located on the reactor vessel to increase the transfer of heat away from the reactor core during an emergency condition.

10. The power module assembly of claim 1 , wherein the flow limiter is configured to release the portion of the coolant in vapor form from the reactor vessel and into the containment vessel during the emergency operation, wherein the containment vessel includes an inner surface facing the reactor vessel, and wherein the inner surface is shaped such that the coolant in vapor form condenses on the inner surface of the containment vessel to reduce a pressure in the containment vessel at a same rate that the coolant in vapor form is released into the containment vessel and adds pressure to the containment vessel.

11. The power module assembly of claim 10 , wherein the coolant in vapor form is released into the containment vessel to remove a decay heat of the reactor core primarily through the condensation of the coolant on the inner surface of the containment vessel.

12. A power module assembly comprising:
a reactor vessel housing a reactor core, wherein the reactor vessel further houses a coolant during a normal mode of operation;
a containment vessel encapsulating the reactor vessel and defining a containment region outside of the reactor vessel, wherein the containment region is completely dry during the normal mode of operation;
a first valve positioned to permit the release of at least a portion of the coolant, in a vapor form, from the reactor vessel and into the containment region during an emergency mode of operation, and wherein the first valve is configured to stop release of the coolant when a pressure in the containment region exceeds a threshold value; and
a second valve, wherein the second valve is a one-way valve positioned to (a) permit at least some of the portion of the coolant received in the containment region to return therethrough back into the reactor vessel after the emergency mode of operation and (b) inhibit the coolant from flowing therethrough from the reactor vessel to the containment vessel during the emergency mode of operation.

13. The power module assembly of claim 12 , wherein the containment vessel is configured to maintain the containment region at at least a partial vacuum during the normal mode of operation.

14. The power module assembly of claim 12 , wherein the containment vessel is configured to maintain the containment region at at least a partial vacuum during the normal mode of operation, and wherein the vacuum is configured to inhibit convective heat transfer from the reactor vessel to the containment region during the normal mode of operation.

15. The power module assembly of claim 12 , wherein the containment vessel is configured to maintain the containment region at at least a partial vacuum during the normal mode of operation, and wherein the vacuum is configured to draw the portion of the coolant through the first valve from the reactor vessel into the containment region during the emergency mode of operation.

16. The power module assembly of claim 15 , wherein, during the emergency mode operation, the vacuum is configured to draw the portion of the coolant through the first valve from the reactor vessel into the containment vessel without using a separate pump or elevated holding tank.

17. The power module assembly of claim 12 , further comprising a reflective insulation located on the reactor vessel to increase the transfer of heat away from the reactor core during an emergency condition.

Assignees

• Nuscale Power Llc

Inventors

• Reyes Jr Jose N
• Groome John T

Classifications

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C13/00

  Pressure vessels; Containment vessels; Containment in general (for chemical or physical processes B01J3/00; pressure vessels in general F16J12/00) · CPC title

• G21C11/08

  Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield {; Thermal insulation} · CPC title

• G21C15/18 Primary

  Emergency cooling arrangements; Removing shut-down heat · CPC title

• G21C9/012 Primary

  by thermal accumulation or by steam condensation, e.g. ice condensers · CPC title