Nuclear reactor cooling arrangement having a stirling engine

Patent metadata

Field	Value
Publication number	US-11302452-B2
Application number	US-201816620553-A
Country	US
Kind code	B2
Filing date	Jun 11, 2018
Priority date	Jun 13, 2017
Publication date	Apr 12, 2022
Grant date	Apr 12, 2022

Abstract

A reactor cooling and power generation system according to the present disclosure includes a reactor vessel, a heat exchange section formed to receive heat generated from a core inside the reactor vessel, from a feedwater system through a fluid, and an electric power production section. A Stirling engine is provided to produce electric energy using the energy of the fluid whose temperature has increased while receiving the heat of the reactor. The system is formed to circulate the fluid that has received heat from the core in the heat exchange section through the electric power production section. The system operates even during a normal operation and during an accident of the nuclear power plant.The reactor cooling and power generation system accompanies a nuclear reactor vessel which includes a reactor coolant system, a feedwater system and a steam generator. A turbine produces electric power from the feed water system.

First claim

What is claimed is:

1. A system, comprising:
a nuclear reactor vessel configured to include a nuclear reactor coolant system and to circulate nuclear reactor coolant of the nuclear reactor coolant system;
a feedwater system for producing electric power connected to the nuclear reactor vessel;
a steam generator inside of the nuclear reactor vessel;
a turbine configured to produce electric power from the feedwater system; and
a nuclear reactor cooling and power generation system configured to produce electric power during an accident of a nuclear power plant to produce electric power,
the nuclear reactor cooling and power generation system for producing electric power comprising:
a heat exchange section formed to include a fluid inside the heat exchange section and formed to receive heat generated from a core inside the nuclear reactor vessel to the fluid during a normal operation of the nuclear power plant; and
an electric power production section comprising a Stirling engine formed to produce electric energy using the energy of the fluid whose temperature has increased while receiving the heat of the nuclear reactor, and
wherein the heat exchange section is fluidly separated from the feedwater system, the steam generator, and the turbine,
wherein during the normal operation of the nuclear power plant, steam produced by the steam generator is passed through a main steam line and supplied to the turbine to produce electric power, and
wherein the nuclear reactor cooling and power generation system is formed to circulate the fluid that has received heat from the core in the heat exchange section through the electric power production section, and operates even during the normal operation and during the accident of the nuclear power plant, to produce electric power.

2. The system of claim 1 , wherein the electric power produced during the normal operation of the nuclear power plant is supplied to an internal and external electric power system and an emergency battery.

3. The system of claim 2 , wherein the electric energy charged in the emergency battery is formed to supply an emergency electric power as an emergency power source during an accident.

4. The system of claim 1 , wherein the electric power produced during an accident of the nuclear power plant is formed to be supplied to an emergency power source of the nuclear power plant.

5. The system of claim 3 , wherein the emergency power source is formed to supply an electric power for the operation of a nuclear safety system or valve manipulating for the operation of the nuclear safety system or monitoring the nuclear safety system or operation of the nuclear reactor cooling and power generation system during an accident of the nuclear power plant.

6. The system of claim 1 , wherein a seismic design of seismic category I, II or III is applied thereto.

7. The system of claim 1 , wherein a safety grade of safety class 1, 2 or 3 is applied thereto.

8. The system of claim 1 , further comprising:
a first discharge section connected to the heat exchange section,
wherein the first discharge section is formed to discharge at least a part of the fluid excessively supplied to the electric power production section.

9. The system of claim 8 , wherein the heat exchange section is formed to surround at least a part of the nuclear reactor vessel, and has a shape capable of cooling an outer wall of the nuclear reactor vessel formed to receive heat discharged from the nuclear reactor vessel that has received heat generated from the core.

10. The system of claim 9 , wherein at least a part of the shape of the heat exchange section having a shape of cooling the outer wall of the nuclear reactor vessel comprises a cylindrical shape, a hemispherical shape, a double vessel shape, or a mixed shape thereof.

11. The system of claim 9 , further comprising:
an in-containment refueling water storage tank (IRWST) configured to supply refueling water to the heat exchange section having a shape capable of cooling the outer wall of the nuclear reactor vessel.

12. The system of claim 11 , further comprising:
a second discharge section provided in a heat exchange section having a shape capable of cooling the outer wall of the nuclear reactor vessel,
wherein the second discharge section is formed to discharge the refueling water supplied from the in-containment refueling water storage tank (IRWST).

13. The system of claim 9 , wherein a coating member is further formed on the heat exchange section having a shape capable of cooling the outer wall of the nuclear reactor vessel to prevent the corrosion of the nuclear reactor vessel.

14. The system of claim 13 , wherein a surface of the coating member is chemically treated to increase a surface area thereof.

15. The system of claim 9 , wherein a heat transfer member is further formed to transfer heat discharged from the nuclear reactor vessel.

16. The system of claim 15 , wherein a surface of the heat transfer member is chemically treated to increase a surface area thereof.

17. The system of claim 8 , wherein the heat exchange section is provided inside the nuclear reactor vessel, and has a shape capable of cooling an inside of the nuclear reactor vessel formed to receive heat discharged from a nuclear reactor coolant system inside the nuclear reactor vessel that has received heat generated from the core.

18. The system of claim 17 , further comprising:
an in-containment refueling water storage tank (IRWST) configured to supply refueling water to the heat exchange section having a shape capable of cooling an inside of the nuclear reactor vessel.

19. The system of claim 18 , further comprising:
a second discharge section is provided in a heat exchange section having a shape capable of cooling the inside of the nuclear reactor vessel, and
wherein the second discharge section is formed to discharge the refueling water supplied from the in-containment refueling water storage tank (IRWST).

20. The system of claim 1 , further comprising:
an evaporator section connected to the heat exchange section,
wherein the evaporator section is formed to exchange heat with an inner fluid of the heat exchange section and an inner fluid of the electric power production section, and comprises a first circulation section formed to circulate through the heat exchange section and the evaporator section; and a second circulation section formed to circulate through the evaporator section and the electric power production section.

21. The system of claim 20 , wherein at least one of the first circulation section and the second circulation section is formed to circulate by a single-phase fluid.

22. The system of claim 1 , wherein the heat exchange section further comprises a core catcher, and the core catcher is formed to receive and cool a melted core when the core is melted in the nuclear reactor vessel.

23. The system of claim 1 , wherein the Stirling engine comprises:
a power generation section comprising a cylinder having a reciprocator and a piston configured to generate motive power by heat received through the fluid that has received heat, and a power transmission section; and
an electricity generation section configured to convert mechanical energy generated by the power generation section into electrical energy.

24. The system of claim 1 , wherein the Stirling engine comprises a first temperature section and a second temperature section respectively filled with workin

Assignees

• Korea Atomic Energy Res
• King Abdullah City For Atomic And Renewable Energy

Inventors

• Kim Youngin
• Bae Youngmin
• Han Hunsik
• Chang Cheongbong
• Kee Junewoo
• Lee Minkyu
• Park Kisun
• Cho Bonghyun

Classifications

• G21C3/40 Primary

  Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat (for temperature measurement G21C17/10 ){or with another arrangement for direct production of electric energy, e.g. a thermionic device (combination with thermoelements for temperature measurements G21C17/102)} · CPC title

• G21D1/02

  Arrangements of auxiliary equipment · CPC title

• F02G1/055

  Heaters or coolers · CPC title

• G21D5/08 Primary

  with engine working medium heated in a heat exchanger by the reactor coolant · CPC title

• Y02E30/00

  Energy generation of nuclear origin · CPC title