Passive containment cooling system for a nuclear reactor

US11569000B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-11569000-B2
Application numberUS-202217836443-A
CountryUS
Kind codeB2
Filing dateJun 9, 2022
Priority dateDec 24, 2019
Publication dateJan 31, 2023
Grant dateJan 31, 2023

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

    Technology tags used to group this patent with similar filings.

  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir due to absorbing heat from the nuclear reactor. A check valve assembly, in fluid communication with the coolant reservoir, selectively enables one-way flow of a containment fluid from the containment environment to the coolant reservoir, based on a pressure at an inlet being equal to or greater than a threshold magnitude. A fusible plug, in fluid communication with the coolant reservoir at a bottom vertical depth below the bottom of the coolant reservoir, enables coolant fluid to flow into the containment structure based on at least partially melting.

First claim

Opening claim text (preview).

The invention claimed is: 1. A method for operating a passive containment cooling system for a nuclear reactor, the method comprising: directing a flow of a coolant fluid downwards out of a lower region of a coolant reservoir via a coolant supply conduit according to gravity to a bottom of a coolant channel that extends vertically along a containment structure that at least partially defines a containment environment in which the nuclear reactor is located; causing the coolant fluid to rise through the coolant channel from the bottom of the coolant channel toward an upper region of the coolant reservoir via a top of the coolant channel according to a change in buoyancy of the coolant fluid based on the coolant fluid absorbing heat rejected from the nuclear reactor in the containment environment via at least the containment structure; and selectively enabling a one-way flow of a containment fluid, from the containment environment to the coolant reservoir through the coolant channel via a first check valve assembly and the coolant channel, the first check valve assembly at a first vertical depth below a top surface of the coolant fluid in the coolant reservoir, the first check valve assembly in fluid communication with the coolant reservoir through the coolant channel and in fluid communication with the containment environment, wherein the selectively enabling is based on one or more check valves of the first check valve assembly opening in response to a pressure at an inlet of the one or more check valves being equal to or greater than a first threshold magnitude, the first threshold magnitude at least partially corresponding to a hydrostatic pressure of the coolant fluid at an outlet of the first check valve assembly at the first vertical depth. 2. The method of claim 1 , wherein the first threshold magnitude is greater than a reference hydrostatic pressure of the coolant fluid at the first vertical depth below the top surface of the coolant fluid in the coolant reservoir that results from the coolant reservoir being filled to a reference reservoir depth. 3. The method of claim 1 , further comprising: inhibiting the one-way flow, subsequently to selectively enabling the one-way flow, based on the one or more check valves closing in response to the pressure of the containment environment at an inlet of the first check valve assembly being less than the first threshold magnitude. 4. The method of claim 1 , wherein the one or more check valves include a series connection of a plurality of check valves between an inlet of the first check valve assembly and the outlet of the first check valve assembly, each check valve of the plurality of check valves is configured to open in response to a pressure at an inlet of the check valve being equal to or greater than the first threshold magnitude, and the selectively enabling is based on all check valves of the series connection of the plurality of check valves opening. 5. The method of claim 1 , wherein the one or more check valves include a parallel connection of a plurality of sets of one or more check valves between an inlet of the first check valve assembly and one or more check valve assembly outlets, each check valve of the plurality of sets of one or more check valves is configured to open in response to a pressure at an inlet of the check valve being equal to or greater than the first threshold magnitude, and the selectively enabling is based on any set of one or more check valves of the parallel connection of the plurality of sets of one or more check valves. 6. The method of claim 1 , wherein the selectively enabling is based on a burst disc coupled in series with the inlet of the one or more check valves and an inlet of the first check valve assembly rupturing in response to a pressure at the inlet of the first check valve assembly at the first vertical depth being equal to or greater than the first threshold magnitude. 7. The method of claim 1 , further comprising: directing at least a portion of the coolant fluid at a bottom vertical depth below the top surface of the coolant fluid in the coolant reservoir to flow into the containment environment via an exposed flow conduit between the coolant reservoir and the containment environment through the coolant channel at the bottom vertical depth to at least partially flood the containment environment, based on a fusible plug in fluid communication with the coolant reservoir through the coolant channel and with the containment environment at the bottom vertical depth, at least partially melting to expose the exposed flow conduit in response to a temperature in the containment environment at an end of the fusible plug that is open to the containment environment being equal to or greater than a threshold temperature. 8. The method of claim 7 , wherein the first check valve assembly, based on selectively enabling the one-way flow, maintains a pressure in the containment environment at the bottom vertical depth at a magnitude that is less than the hydrostatic pressure of the coolant fluid at the bottom vertical depth, to enable flow of the coolant fluid through the exposed flow conduit and into the containment environment in response to the fusible plug at least partially melting.

Assignees

Inventors

Classifications

  • the valve comprising fusible, softening or meltable elements, e.g. used as link, blocking element, seal, closure plug (F16K17/386 takes precedence) · CPC title

  • Partitions or thermal insulation between fuel channel and moderator · CPC title

  • Reactor fuses · CPC title

  • by an absorbent fluid · CPC title

  • Rupture diaphragms · CPC title

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Frequently asked questions

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What does patent US11569000B2 cover?
A nuclear plant includes a nuclear reactor, a containment structure that at least partially defines a containment environment of the nuclear reactor, and a passive containment cooling system that causes coolant fluid to flow downwards from a coolant reservoir to a bottom of a coolant channel coupled to the containment structure and rise through the coolant channel toward the coolant reservoir d…
Who is the assignee on this patent?
Ge Hitachi Nuclear Energy Americas Llc
What technology area does this patent fall under?
Primary CPC classification G21C15/18. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Jan 31 2023 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).