Passive containment system
閱讀：325發(fā)布：2022-02-01
專利匯可以提供Passive containment system專利檢索，專利查詢，專利分析的服務。并且A containment system that provides complete protection entirely by passive means for the loss of coolant accident in a nuclear power plant and wherein all stored energy released in the coolant blowdown is contained and absorbed while the nuclear fuel is prevented from over-heating by a high containment back-pressure and a reactor vessel refill system. The primary containment vessel is restored to a high subatmospheric pressure within a few minutes after accident initiation and the decay heat is safely transferred to the environment while radiolytic hydrogen is contained by passive means.，下面是Passive containment system專利的具體信息內容。
1. A safeguard system for a nuclear reactor power plant having a reactor assembly with a reactor core including fuel therein, at least one steam generator, said steam generator having a first operative connection to said reactor assembly for the flow of a high-temperature high-pressure reactor coolant therethrough, said reactor coolant having a first pressure the magnitude of which is substantially constant during conditions of normal operation, and a containment structure sealingly enclosing at least said reactor and said steam generator, said safeguard system comprising at least one reservoir of cooling liquid disposed generally internally of said containment structure, said cooling liquid being pressurized to a second predetermined pressure the magnitude of which during conditions of normal operation is less than the magnitude of said first pressure thereby defining a first predetermined pressure differential, first conduit means for communicating between said cooling liquid and said reactor assembly, and second conduit means for communicating between said steam generator and said cooling liquid, said first conduit means being effective to supply a flow of said cooling liquid to said reactor assembly whenever there is an accidential loss of said reactor coolant causing a reduction in the magnitude of said first pressure sufficient to attain a second predetermined pressUre differential as between said cooling liquid and said reactor coolant within said reactor assembly, said second predetermined pressure differential having a magnitude less than said first predetermined pressure differential, said flow of said cooling liquid being directed to said reactor core to thereby replenish said accidental loss of said reactor coolant, said second conduit means being effective when a third predetermined pressure differential is attained between said cooling liquid and the steam within said steam generator for supplying comparatively high pressure steam to said cooling liquid to thereby provide a pumping force to said cooling liquid to completely fill that portion of the reactor assembly containing the fuel of said reactor core.
2. A safeguard system according to claim 1 wherein said cooling liquid is pressurized by associated pump means.
3. A safeguard system according to claim 1 wherein said reservoir of cooling liquid comprises at least one normally closed tank-like structure containing said cooling liquid, and wherein said cooling liquid comprises water with a neutron poison carried thereby.
4. A safeguard system according to claim 3 wherein said neutron poison is of such a concentration so that when said steam generator forces said cooling liquid out of said reservoir completely filling that portion of the reactor assembly containing the fuel of said reactor core the cooling fluid so filling that said portion of the reactor has the required and sufficient concentration of said neutron poison.
5. A safeguard system according to claim 3 and further comprising steam jet injector nozzles operatively communicating with said cooling liquid said first conduit means and said second conduit means whereby when communication is completed through said second conduit means the flow of steam therethrough and said jet injector nozzles causes a flow of said cooling liquid out of said tank-like structure and through said jet injector nozzles into said first conduit means.
6. A safeguard system according to claim 1 and further comprising third conduit means communicating between said reservoir and said steam generator, said third conduit means being effective when the pressure of the steam within said steam generator exceeds a predetermined design maximum pressure to vent such steam to said cooling liquid within said reservoir.
7. A safeguard system according to claim 6 and further comprising pressure responsive valve means effective for completing communication through said third conduit means when said steam pressure exceeds said predetermined design maximum pressure, said pressure responsive valve means being effective to prevent said communication through said third conduit means when said steam pressure does not exceed said predetermined design maximum pressure.
8. A safeguard system according to claim 1 and further comprising pressure responsive means effective for preventing flow of steam from said steam generator through said second conduit means to said reservoir until a pressure differential therebetween is attained equal to said third predetermined pressure differential.
9. A safeguard system according to claim 8 wherein said pressure responsive means comprises rupture disk means.
10. A safeguard system according to claim 6 and further comprising pressure responsive means effective for preventing flow of steam from said steam generator through said second conduit means to said reservoir until a pressure differential therebetween is attained equal to said third predetermined pressure differential.
11. A safeguard system according to claim 10 wherein said pressure responsive means comprises rupture disk means.
12. A safeguard system according to claim 1 and further comprising means for determining a maximum flow rate from said steam generator through said second conduit means to said reservoir, said means for determining said maximum flow rate comprising sonic orifice means in series with said second conduit means.
13. A safeguard system according to claim 6 and further comprising means for determining a maximum flow rate from said steam generator through said second conduit means to said reservoir, said means for determining said maximum flow rate comprising sonic orifice means in series with said second conduit means.
14. A safeguard system according to claim 1 wherein said cooling liquid within said reservoir is refrigerated to a low temperature but still maintaining its liquid state so as to thereby be capable of absorbing additional quantities of energy when directed to the environs of said portion of said reactor assembly.
15. A safeguard system according to claim 1 wherein said cooling liquid is de-airated so as to thereby remove substantially all of the free oxygen therefrom and thereby prevent the possibility of an oxygen supported hydrogen explosion when said cooling liquid is directed to the environs of said portion of said reactor assembly.
16. A safeguard system according to claim 1 and further comprising a second body of a second cooling liquid disposed generally within said containment structure, third conduit adapted for communication between said second cooling liquid and the interior of said containment structure, and pressure responsive means cooperating with said third conduit means for normally preventing flow of said second cooling liquid into said interior of said containment structure, said pressure responsive means being effective to complete said communication through said third conduit means whenever said interior of said containment structure attains a predetermined increased pressure arising out of said accidental loss of said reactor coolant into said interior of said containment structure, the said completion of said communication through said third conduit means enabling said second cooling liquid to absorb some of the heat energy of said accidentally lost reactor coolant and to flow into said interior of said containment structure and into heat exchanging relationship with said reactor assembly.
17. A safeguard system according to claim 16 wherein the respective volumes of said interior of said containment structure said reactor assembly said first mentioned cooling liquid and said second cooling liquid are such as to cause said interior of said containment structure to be at a pressure less than atmospheric pressure once said first mentioned cooling liquid and said second cooling liquid have been directed to the environs of said reactor assembly.
18. A safeguard system according to claim 1 wherein said reservoir comprises a plurality of spaced tank structures each of which is filled with said cooling liquid, and further comprising an additional quantity of steam generators collectively referred to with said at least one steam generator as a plurality of steam generators, wherein said first conduit means interconnect respective ones of all of said plurality of spaced tank structures and said reactor assembly, and wherein said second conduit means interconnect respective ones of said plurality of steam generators to respective ones of said plurality of spaced tank structures.
19. A safeguard system according to claim 18 wherein said reactor assembly comprises inlet means and outlet means for the normal flow of said reactor coolant therethrough, and wherein said first conduit means are operatively connected to both said inlet means and said outlet means.
20. In a nuclear reactor power plant comprising a reactor assembly, reactor assembly coolant system means comprising reactor coolant conduit means, high-pressure high temperature reactor coolant circulated within said reactor coolant system, steam generator means, and a containment structure sealingly enclosing at least said reactor assembly and said reactor coolant system means, the method of affecting containment of said reactor power plant during accidental loss of said reactor coolant from said reactor coolant system means, said method comprising the steps of sensing the occurrence oF said accidental loss of said reactor coolant by means of the occurrence of a first preselected pressure differential between said reactor coolant within said reactor coolant system and a first separate body of pressurized cooling liquid, causing said cooling liquid to start to flow to and into said reactor coolant system means and in so doing reducing the pressure magnitude of said pressurized cooling liquid, sensing the decreasing pressure magnitude of said pressurized cooling liquid until a second preselected pressure differential is attained between said pressurized cooling liquid and the steam within said steam generator means, and causing said steam to be directed to said pressurized cooling liquid when said second preselected pressure differential is attained to thereby provide an additional pumping force to said cooling liquid to thereby continue said flow of said cooling liquid to and into said reactor coolant systems means in order to thereby replenish such of said reactor coolant as has been lost due to the occurence of said accidental loss of said reactor coolant.
21. A method according to claim 20 and further comprising the step of chilling said pressurized cooling liquid prior to the attainment of said first preselected pressure differential.
22. A method according to claim 20 and further comprising the steps of permitting such reactor coolant as is lost during said accidental loss of reactor coolant to vaporize within said containment structure so as to cause the interior of said containment structure to attain a first relatively high vapor pressure, sensing the attainment of a third selected pressure differential occurring between said interior of said containment structure and a second separate body of second cooling liquid when said first relatively high vapor pressure is attained, then completing communication between vapor at said relatively high vapor pressure and said second cooling liquid to thereby heat and simultaneously pressurize said second cooling liquid, and permitting said second cooling liquid to flood said interior of said containment structure when the total effective pressure head of said second coolinq liquid exceeds the existing magnitude of said vapor within said containment structure.
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