SU449655A1 - System for limiting the consequences of a nuclear power plant accident - Google Patents
System for limiting the consequences of a nuclear power plant accidentInfo
- Publication number
- SU449655A1 SU449655A1 SU1781252A SU1781252A SU449655A1 SU 449655 A1 SU449655 A1 SU 449655A1 SU 1781252 A SU1781252 A SU 1781252A SU 1781252 A SU1781252 A SU 1781252A SU 449655 A1 SU449655 A1 SU 449655A1
- Authority
- SU
- USSR - Soviet Union
- Prior art keywords
- channel
- consequences
- power plant
- limiting
- nuclear power
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
- G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
(54) СИСТЕМА ОГРАНИЧЕНИЯ ПОСЛЕДСТВИЙ АВАРИИ НА АТОМНОЙ ЭЛЕКТРОСТАНЦИИ(54) SYSTEM OF LIMITED CONSEQUENCES OF AN ACCIDENT AT A NUCLEAR POWER PLANT
7, нагнетающих воздух из канала 2 в помещение 1 первого контура. Насосы 8 предназначены дл подачи хладагента к теплообменникам 9 и ионообменным фильтрам Ю.7, forcing air from the channel 2 into the room 1 of the first circuit. Pumps 8 are designed to supply refrigerant to heat exchangers 9 and ion exchange filters Yu.
При нормальной эксплутапии вентил торы 7 отсасывают охлажденный в устройстве 4 воздух из канала 2 и нагнетают его в помещение 1 первого контура. Нагретый воздух из помещени 1 проходит через посто нно снабжаемую хладагентом часть устройства 4 дл конденсации и снова отсасываетс вентил торами . Использованный хладагент стекает вниз отсасываетс насосами 8, охлаждаетс втеплообменниках 9, очищаетс в ионообменных фильтрах 10 и возвращаетс в емкость 5.During normal operation, the fans 7 suck off the air cooled in the device 4 from the channel 2 and inject it into the room 1 of the first circuit. The heated air from room 1 passes through a part of the condenser device 4 which is constantly supplied with refrigerant and is again sucked off by fans. The used refrigerant flows down and is sucked off by pumps 8, is cooled in heat exchangers 9, cleaned in ion exchange filters 10 and returned to tank 5.
При аварии с разрывом главного трубопровода пар, образующийс при вскипании теплоносител , заполн ет помещение 1, вытесн наход щийс в нем воздух через устройство 4 дл конденсации в вентил ционный канал 2, Давление в канале повыщаетс , срабатывает клапанна система 3, и воздух, а затем и малоактивна паровоздущна смесь сбрасываютс за пределы аварийного помещени , например в окружающую среду. В начальный период времени аварии, когда в помещении 1 и канале 2 начинает возрастать давление, открываютс клапаны емкости5Ги хладагент из этой емкости начинает поступать в раздающее устройство, а затем - в устройство 4 дл конденсации. Через некоторое врем (5-15 сек расход пара через устройство 4 снижаетс в несколько раз по сравнению с первоначальным из-за уменьщени течи теплоносител из первого контура, св занного с падением давлени в нем. К этому времени расход хладагента через устройство 4 возрастает до такой величины, котора позвол ет сконденсировать весь поступающий в помещение 1 и канал 2 пар. В результате конденсации давление в помещении 1 и канале 2 быстро снижаетс , и клапанна система 3 закрываетс . Это происходит до того, как начнетс массова разгерметизаци тепловыдел ющих элементов , а значит, и выход больщого количества радиоактивных продуктов делени .In the event of an accident with the main pipeline rupture, the steam generated during the boiling up of the coolant fills the room 1, the air in it is forced out through the device 4 for condensation into the ventilation channel 2, the pressure in the channel rises, the valve system 3 is triggered, and the air, and then and a low-active vapor-air mixture is dumped outside the emergency room, for example, into the environment. In the initial period of the time of the accident, when the pressure in room 1 and channel 2 begins to increase, the valves of the tank 5G and the refrigerant from this container start to flow into the dispensing device, and then into the device 4 for condensation. After some time (5–15 s, steam consumption through device 4 decreases several times as compared to the initial one due to a decrease in coolant leak from the primary circuit associated with a pressure drop in it. By this time, the flow rate of refrigerant through device 4 increases to all that enters room 1 and channel 2, the condensation pressure in room 1 and channel 2 rapidly decreases, and the valve system 3 closes. This happens before mass loss of pressure occurs. heat generating elements, and hence the output bolschoy quantities of radioactive fission products.
После закрыти клапанной системы 3 в помещении 1 и канале 2 устанавливаетс достаточно глубокое разрежение, поскольку значительна часть воздуха в первый период аварии была вытеснена за пределы аварийного помещени , а пар, вытеснивщий воздух, конденсируетс . Дл удалени воздуха из аварийного помещени , который рециркулирует с помощью вентил торов 7, основного количества наиболее опасных радиоактивных продуктов, в первую очередь У 131 и аэрозолей, достаточно 2-5 час. Давление в аварийном помещении в течение этого времени продолжает оставатьс ниже атмосферного несмотр на присосы из окружающей среды через неплотности.After closing the valve system 3 in room 1 and channel 2, a sufficiently deep vacuum is established, since a significant part of the air was forced out of the emergency room during the first period of the accident, and the vapor displacing air condenses. To remove air from the emergency room, which is recirculated with the help of fans 7, the main amount of the most dangerous radioactive products, first of all, 131 and aerosols, is 2-5 hours long enough. The pressure in the emergency room during this time continues to remain below atmospheric despite the suction from the environment through leaks.
Claims (2)
Priority Applications (9)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE791572D BE791572A (en) | 1972-03-30 | METHOD AND SYSTEM FOR LIMITING THE FOLLOW-UP OF A DAMAGE IN ATOMIC POWER PLANTS | |
SU1781252A SU449655A1 (en) | 1972-05-05 | 1972-05-05 | System for limiting the consequences of a nuclear power plant accident |
BG21912A BG20737A1 (en) | 1972-03-30 | 1972-11-20 | |
DD167016A DD102848A1 (en) | 1972-03-30 | 1972-11-22 | |
DE2257790A DE2257790A1 (en) | 1972-05-05 | 1972-11-24 | Nuclear power station damage control - with containment system for leaking coolant |
FR7242872A FR2177700A1 (en) | 1972-03-30 | 1972-12-01 | Nuclear power station damage control - with containment system for leaking coolant |
RO197273029A RO63470A (en) | 1972-03-30 | 1972-12-04 | METHOD AND INSTALLATION FOR LIMITING TRACTORS OF DAMAGE TO NUCLEAR POWER PLANTS |
IT33148/72A IT974734B (en) | 1972-03-30 | 1972-12-19 | PROCEDURE AND SYSTEM TO LIMIT THE CONSEQUENCES OF FAILURES IN ATOMIC POWER PLANTS MAINLY TO THE LOSS OF THE CALO RE VEHICLE FROM THE FIRST CIRCUIT |
CS2325A CS160475B1 (en) | 1972-03-30 | 1973-03-30 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SU1781252A SU449655A1 (en) | 1972-05-05 | 1972-05-05 | System for limiting the consequences of a nuclear power plant accident |
Publications (1)
Publication Number | Publication Date |
---|---|
SU449655A1 true SU449655A1 (en) | 1977-01-25 |
Family
ID=20513190
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SU1781252A SU449655A1 (en) | 1972-03-30 | 1972-05-05 | System for limiting the consequences of a nuclear power plant accident |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE2257790A1 (en) |
SU (1) | SU449655A1 (en) |
-
1972
- 1972-05-05 SU SU1781252A patent/SU449655A1/en active
- 1972-11-24 DE DE2257790A patent/DE2257790A1/en active Pending
Also Published As
Publication number | Publication date |
---|---|
DE2257790A1 (en) | 1973-10-11 |
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