# US 12,763,225 B2 · System including emergency core cooling system valve for nuclear reactor

> Agents: this data is available as JSON from the patentgrep API and MCP server — see https://patentgrep.com/llms.txt

- Number: US 12,763,225 B2
- Document ID: US12763225B2
- Status: Granted
- Kind: B2
- Application number: 18/278,458
- Filed: 2021-11-01
- Published: 2024-05-09
- Granted: 2026-10-13
- Earliest claimed: 2021-03-10
- Assignees: Korea Atomic Energy Research Institute
- Applicants: Korea Atomic Energy Research Institute
- Inventors: Soo Jai Shin; Cheongbong Chang; Seungyeob Ryu; Han-Ok Kang; Young-In Kim; Ji Han Chun; Sung Won Lim; Joo Hyung Moon; Hun Sik Han; Seok Kim; Hyunjun Cho
- Web page: https://patentgrep.com/patent/US12763225B2

## CPC

- G21C 15/18: Emergency cooling arrangements; Removing shut-down heat
- G21C 15/12: from pressure vessel; from containment vessel
- G21C: NUCLEAR REACTORS (fusion reactors, hybrid fission-fusion reactors G21B; nuclear explosives G21J)

## Abstract

A system comprising an emergency core cooling system (ECCS) valve, a nuclear reactor vessel, and a containment vessel surrounding the nuclear reactor vessel, is provided. The ECCS valve comprises an outer shell connected to the nuclear reactor vessel and protruding toward the containment vessel and having a connector formed therein; an inner shell provided inside the outer shell at a preset distance from an inner wall of the outer shell; a piston movably constrained and inserted through a piston opening formed in the inner shell at a position facing the connector of the outer shell to open and close the connector; a spring provided on an outer circumferential surface of the piston to provide a restoring force for moving the piston in a direction toward the nuclear reactor vessel; a fluid pump; a swing check valve; a reset valve; and a trip valve.

## Claims

### Claim 1

A system comprising:
an emergency core cooling system (ECCS) valve;
a nuclear reactor vessel; and
a containment vessel surrounding the nuclear reactor vessel,
wherein the ECCS valve is provided between
the nuclear reactor vessel
and the containment vessel,
and the ECCS valve is configured to supply
a coolant, that is filled in a containment space formed between the nuclear reactor vessel and the containment vessel,
to the nuclear reactor vessel
in the event of a loss of coolant accident (LOCA), and
wherein the ECCS valve comprises:
an outer shell
connected to the nuclear reactor vessel
and protruding toward the containment vessel
and having a connector formed therein
so as to communicatively connect an interior of the nuclear reactor vessel to the containment space;
an inner shell provided inside the outer shell
at a preset distance from an inner wall of the outer shell;
a piston movably constrained and inserted through a piston opening formed in the inner shell
at a position facing the connector of the outer shell to open and close the connector;
a spring provided on an outer circumferential surface of the piston to provide a restoring force for moving the piston in a direction toward the nuclear reactor vessel,
a fluid pump configured to supply fluid to an inside of the inner shell between the nuclear reactor vessel and a bottom portion of the piston;
a swing check valve
provided to pivotally hinge on an inner wall of the inner shell on the side of the nuclear reactor vessel
and opening and closing an inner shell opening between the nuclear reactor vessel and the inner shell
according to
an internal pressure of the nuclear reactor vessel
and a fluid pressure supplied from the fluid pump into the inner shell;
a reset valve
connected to the fluid pump and
supplying, by opening, a fluid from the fluid pump
to the inside of the inner shell between the nuclear reactor vessel and the bottom portion of the piston; and
a trip valve
opened
during malfunction of the reset valve
or by an operating signal
and operating to reduce an internal pressure of the inner shell,
wherein the piston operates to open the connector
when a difference between
an internal pressure of the nuclear reactor vessel
and an internal pressure of the containment vessel
is less than the restoring force of the spring,
wherein the inner shell shares an inner wall with the outer shell.

### Claim 2 (depends on 1)

The system of claim 1, wherein:
the piston includes
a body portion inserted into the piston opening of the inner cell;
a head portion integrally formed with the body portion on one side of the body portion and contacting the connector; and
a bottom portion integrally formed with the body portion on the other side of the body portion and provided inside the inner shell.

### Claim 3 (depends on 2)

The system of claim 2, wherein:
the spring
is interposed between an inner wall of the inner shell and the bottom portion of the piston inside the inner shell.

### Claim 4 (depends on 2)

The system of claim 2, wherein:
the piston opening
is sealed by inserting the body portion of the piston thereinto.

### Claim 5 (depends on 2)

The system of claim 2, wherein:
the head portion
includes an inclined surface inclined toward the connector on a cross section, and the inclined surface contacts an edge of the connector so that the head portion seals the connector.

### Claim 6 (depends on 5)

The system of claim 5, wherein:
the outer shell
has a protruding shape directed toward the containment vessel in a form corresponding to the inclined surface of the head portion.

### Claim 7 (depends on 2)

The system of claim 2, wherein:
the head portion
includes a stepped surface stepped toward the connector, and the stepped surface contacts an edge of the connector so that the head portion seals the connector.

### Claim 8 (depends on 2)

The system of claim 2, wherein:
the head portion includes a stepped surface, and
the spring is interposed between the stepped surface of the head portion and an inner wall of the outer shell.

### Claim 9 (depends on 1)

The system of claim 1, further comprising:
an isolation valve connected to the outer shell to be communicatively connected to the connector and configured to be opened by an operation signal in the event of the LOCA.
