[미국특허]
Low pressure reactor safety systems and methods
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21C-009/00
G21D-001/02
G21C-015/18
G21D-003/06
출원번호
US-0425985
(2012-03-21)
등록번호
US-9460818
(2016-10-04)
발명자
/ 주소
Bergman, Mark A.
출원인 / 주소
GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
대리인 / 주소
Ryan Alley Intellectual Property Law
인용정보
피인용 횟수 :
1인용 특허 :
10
초록▼
A supplementary injection device is installed in a nuclear power plant to draw coolant and inject coolant using an entraining fluid. The injection device can be a venturi or other passive device operable at relatively low fluid pressure that draws coolant through suction at the venturi narrowing poi
A supplementary injection device is installed in a nuclear power plant to draw coolant and inject coolant using an entraining fluid. The injection device can be a venturi or other passive device operable at relatively low fluid pressure that draws coolant through suction at the venturi narrowing point and mixes the coolant with the fluid for injection. The injection device is operable with a known BWR design, where the device is attached to a steam connection to the main steam line of the reactor, a coolant connection drawing from suction lines to a suppression cool or condensate tank, and an outlet connection injecting into the main feedwater lines. In a BWR, the injection device is operable without electricity and at a wide range of pressures, even less than 50 pounds per square inch, to maintain coolant levels in the reactor.
대표청구항▼
1. A coolant injection system for supplementing an RCIC system in a nuclear reactor, the system comprising: the nuclear reactor;a coolant source including a suppression pool;an injection device configured to suck a liquid coolant against gravity;the RCIC system including an RCIC turbine, an RCIC pum
1. A coolant injection system for supplementing an RCIC system in a nuclear reactor, the system comprising: the nuclear reactor;a coolant source including a suppression pool;an injection device configured to suck a liquid coolant against gravity;the RCIC system including an RCIC turbine, an RCIC pump powered by the RCIC turbine, and an RCIC line connecting steam to the RCIC turbine from the nuclear reactor;a steam connection connecting steam from the RCIC line to the injection device before the RCIC turbine;a coolant connection connecting the liquid coolant from the suppression pool to the injection device; andan outlet connection connecting the steam and the liquid coolant to the nuclear reactor, wherein the injection device is configured to entrain the liquid coolant in the steam and inject the entrained liquid coolant and steam into the nuclear reactor, and wherein there are no pumps or turbines along the outlet connection between the injection device and the nuclear reactor. 2. The system of claim 1, wherein the steam is at less than 150 pounds per square inch pressure. 3. The system of claim 1, wherein the injection device is a venturi including a narrowing section configured to increase a velocity and reduce a pressure of the steam flowing through the narrowing section. 4. The system of claim 3, wherein the venturi connects to the coolant connection at the narrowing section so as to draw the liquid coolant into the venturi with the pressure. 5. The system of claim 3, wherein the venturi further includes a diffuser section configured to increase a pressure of the entrained liquid coolant and steam. 6. The system of claim 1, wherein, the nuclear reactor is a light water reactor,the RCIC line is a line connecting a main steam line of the reactor to the steam connection,the coolant connection is a line connecting the suppression pool of the reactor to the injection device, andthe outlet connection is a line connecting the injection device to a main feedwater line of the reactor. 7. The system of claim 6, wherein the suppression pool is below the reactor and below the injection device, and wherein the coolant connection is a line running upward from below a coolant level in the suppression pool to the injection device. 8. The system of claim 6, wherein the main steam line connects to a turbine with a generator to produce electricity, and wherein the steam connection diverts from the main steam line before the turbine. 9. The system of claim 6, wherein the steam connection includes a steam diversion line diverting from the RCIC line that diverts from the main steam line, and wherein the main feedwater line is connected to the reactor and a coolant source that provides only liquid water coolant. 10. The system of claim 1, wherein at least one of the steam connection, the coolant connection, and the outlet connection includes a swing check valve to control operation of the system. 11. The system of claim 1, wherein the injection device is configured to entrain a volumetric flow rate of the liquid coolant sufficient to maintain a liquid coolant level in the reactor when the reactor is generating only decay heat. 12. The system of claim 1, wherein the coolant is entirely below the injection device, and wherein the injection device is configured to entrain the coolant by suction up through the coolant connection. 13. The system of claim 1, wherein the coolant is entirely below the injection device, wherein the injection device is passive and includes no moving parts, and wherein the injection device is configured to draw the coolant up through the coolant connection to the injection device when the steam is at about 50 pounds per square inch of pressure. 14. The system of claim 1, wherein the coolant source is a reservoir holding liquid coolant with a top level entirely below the injection device, and wherein the coolant connection connects between the injection device to below the top level in the reservoir. 15. The system of claim 14, wherein the injection device is a venturi, and wherein the coolant connection connects to the venturi at a narrowest portion of the venturi. 16. The system of claim 15, further comprising: a main steam line connecting the reactor to a turbine with electrical generator, wherein the steam connection diverts from the RCIC line to the venturi. 17. The system of claim 16, wherein the reactor is in a shut down condition and provides steam that is at less than 150 pounds per square inch pressure in the reactor and the main steam line, and wherein the venturi is configured to entrain the liquid coolant in the steam and inject the liquid coolant and steam into the reactor. 18. A coolant injection system for providing coolant in a shutdown nuclear reactor, the system comprising: a decay-heat driven system including a turbine, a pump, and a coolant source, wherein the turbine is configured to extract power from steam generated in the shutdown nuclear reactor to power the pump, and wherein the pump is configured to inject liquid coolant from the coolant source into the shutdown nuclear reactor under power from the turbine;an injection device configured to entrain the liquid coolant in the steam at steam pressures below which the turbine cannot operate the pump, wherein the injection device is configured to entrain the liquid coolant in the steam without electrical power;a steam connection connecting the steam from the shutdown nuclear reactor to the injection device, wherein the steam connection connects directly to the shutdown nuclear reactor and the injection device and consists only of piping and a valve controlling steam flow through the steam connection;a coolant connection connecting the liquid coolant from the liquid coolant source to the injection device, wherein the injection device consists only of a venturi with the coolant connection connecting to the venturi at a narrowest flow area of the venturi, and wherein the coolant connection connects directly to the liquid coolant source and the injection device and consists only of piping and a valve controlling liquid water flow through the coolant connection; andan outlet connection connecting the steam and the liquid coolant as entrained in the injection device to the nuclear reactor, wherein the outlet connection connects directly to the injection device and the shutdown nuclear reactor and consists only of piping and a valve controlling entrained steam and liquid water flow through the outlet connection.
Dagard, Philippe, Method and device for feeding at least one steam generator of a pressurized-water nuclear reactor during periods of reactor shutdown.
Graham, Thomas G., PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel.
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