CN110648770B - Overpressure protection system for reactor cabin - Google Patents
Overpressure protection system for reactor cabin Download PDFInfo
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- CN110648770B CN110648770B CN201911017132.4A CN201911017132A CN110648770B CN 110648770 B CN110648770 B CN 110648770B CN 201911017132 A CN201911017132 A CN 201911017132A CN 110648770 B CN110648770 B CN 110648770B
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- pressure
- pressure relief
- pipe
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- water
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
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- 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
- G21C9/008—Pressure suppression by rupture-discs or -diaphragms
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- 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
Abstract
The invention discloses a reactor cabin overpressure protection system which comprises a pressure relief pipe, a multi-stage pressure relief assembly, a pressure suppression assembly and a sewage tank, wherein the inlet end of the pressure relief pipe is communicated with the interior of a reactor cabin; the multistage pressure relief assembly is arranged in the pressure relief pipe or on a bypass branch pipe of the pressure relief pipe; the pressure-restraining component is communicated with the pressure-relief pipe; an inlet of the sewage tank is communicated with the bottom of the reactor cabin through a safe drainage pipeline, and an outlet of the sewage tank is communicated with the radioactive wastewater treatment system; the pressure relief assembly comprises a pressure relief valve and a primary rupture disk, the pressure relief valve is arranged on the bypass branch pipe, the primary rupture disk is arranged in the pressure relief main pipe, and the connecting point of the bypass branch pipe and the pressure relief pipe is positioned at two ends of the primary rupture disk; the pressure relief assembly further comprises a second-stage rupture disk, and the second-stage rupture disk is arranged in the pressure relief pipe. The invention has the beneficial effects that: the overpressure protection system utilizes the multistage pressure relief assembly to perform staged pressure relief treatment and overpressure protection on the reactor cabin after the coolant leaks.
Description
Technical Field
The invention relates to the field of nuclear safety engineering design, in particular to a reactor cabin overpressure protection system.
Background
As the heart of a nuclear powered vessel, the safe operation of the reactor is of great importance. The reactor, the steam generator, the circulating pump, the pressure stabilizer, the coolant pipeline and the like form a nuclear steam supply system (a loop) which is arranged in the reactor cabin. When a coolant pipeline is damaged, a coolant leakage accident occurs, which is also a serious accident in nuclear safety design, and high-temperature and high-pressure coolant (water) immediately turns into water vapor after entering a reactor cabin, so that the internal pressure of the reactor cabin rapidly rises.
After a coolant leakage accident occurs, even if the reactor stops running, the continuously leaked coolant still causes the internal pressure of the reactor cabin to continuously rise, and the equipment safety in the reactor cabin is influenced; meanwhile, water vapor generated by leakage has radioactivity, and if the structure of the reactor cabin is damaged, radioactive substances are leaked into the cabin, so that the safety of ship personnel can be endangered. Therefore, a reactor bay overpressure protection system must be provided to provide overpressure protection for the reactor under various abnormal operating conditions/accidents, and to act as a nuclear shield with the reactor bay to contain the leaking radioactive materials.
Disclosure of Invention
The invention aims to provide a reactor cabin overpressure protection system aiming at the defects of the prior art, and solves the problems that the safety of a reactor cabin and internal equipment is influenced due to overlarge internal pressure of the reactor cabin caused by leakage of a coolant in the prior art.
The technical scheme adopted by the invention is as follows: a reactor cabin overpressure protection system comprises a pressure relief pipe, a multi-stage pressure relief assembly, a pressure suppression assembly and a sewage tank, wherein the inlet end of the pressure relief pipe is communicated with the interior of a reactor cabin; the multistage pressure relief assembly is arranged in the pressure relief pipe or on a bypass branch pipe of the pressure relief pipe; the pressure-restraining component is communicated with the pressure-relief pipe; an inlet of the sewage tank is communicated with the bottom of the reactor cabin through a safe drainage pipeline, and an outlet of the sewage tank is communicated with the radioactive wastewater treatment system; the sewage tank is connected with a vacuum-pumping system.
According to the scheme, the multistage pressure relief assembly comprises the pressure relief valve and the one-level rupture disk, the pressure relief valve is installed on the bypass branch pipe, the one-level rupture disk is arranged in the pressure relief main pipe, and the connecting points of the bypass branch pipe and the pressure relief pipe are located at two ends of the one-level rupture disk.
According to the scheme, the multistage pressure relief assembly further comprises a second-stage rupture disk, the second-stage rupture disk is arranged in the pressure relief pipe, and the second-stage rupture disk is located at the downstream position of the connecting point of the main flow dividing pipe and the pressure relief pipe; the outlet end of the pressure relief pipe is communicated with an emergency exhaust system; the opening pressures of the pressure release valve, the first-stage rupture disk and the second-stage rupture disk are sequentially increased.
According to the scheme, the pressure suppression assembly comprises a pressure suppression groove and a flow distribution assembly arranged in the pressure suppression groove, wherein pressure suppression water is arranged in the pressure suppression groove, the horizontal plane of the pressure suppression water divides the interior of the pressure suppression groove into a water space at the lower part and an air space at the upper part, the water space is communicated with the sewage tank through a drain valve, and the air space is respectively communicated with the blow-washing system and the vacuum pumping system; the flow dividing assembly comprises a flow divider and a plurality of perforated pipes which are mutually parallel and communicated with the flow dividing main pipe; the flow divider is connected with the pressure relief pipe, and the connection point of the flow divider and the pressure relief pipe is positioned at the downstream of the connection point of the bypass branch pipe and the pressure relief pipe; the porous pipe is completely submerged in the suppression water of the suppression tank.
According to the scheme, the gas space of the pressure-restraining tank is communicated with the top inlet of the steam-water separator, the gas outlet of the steam-water separator is communicated with the waste gas treatment system, and the liquid outlet of the steam-water separator is communicated with the sewage tank through the water outlet pipeline; the top of the sewage tank is communicated with an exhaust system or a vacuum-pumping system.
According to the scheme, the water space of the pressure-restraining groove is communicated with the water replenishing pipeline arranged outside, and the water replenishing pipeline is provided with the water replenishing valve.
According to the scheme, the sewage tank is provided with the liquid level sensor and the pressure sensor.
According to the scheme, the pressure relief valves, the first-stage rupture discs and the second-stage rupture discs are all configured in groups, and each group comprises two pressure relief valves; and the pipeline between the two pressure release valves, the pipeline between the two first-stage rupture discs and the pipeline between the two second-stage rupture discs are respectively connected with a vacuum pumping system.
According to the scheme, the outlet end of the pressure relief pipe is provided with the filtering module.
According to the scheme, a liquid level sensor, a temperature sensor and a pressure sensor are arranged in the pressure suppression groove.
The beneficial effects of the invention are as follows: the overpressure protection system disclosed by the invention utilizes the multistage pressure relief assembly to perform staged pressure relief treatment and overpressure protection on the reactor cabin after the coolant leaks, high-pressure steam generated due to an accident is discharged in time, the internal pressure rise of the reactor cabin is effectively inhibited, the safety of the reactor cabin and internal equipment is protected, and meanwhile, radioactive substances are temporarily sealed and stored, so that accidental leakage of the radioactive substances is avoided.
Drawings
Fig. 1 is a schematic structural diagram of an embodiment of the present invention.
Fig. 2 is a pressure control flow chart of the present embodiment.
Wherein: 1. a reactor compartment; 2. a pressure relief valve; 3. a first-level rupture disk; 4. a pressure relief pipe; 5. a secondary rupture disk; 6. a filtration module; 7. a flow divider; 8. a pressure-restraining groove; 9. a perforated pipe; 10. a steam-water separator; 11. a water replenishing valve; 12. a drain valve; 13. an exhaust valve; 14. a sewage tank; 15. a safety drain valve; 16. a safe drainage pipeline.
Detailed Description
For a better understanding of the present invention, reference is made to the following detailed description taken in conjunction with the accompanying drawings.
The overpressure protection system of the reactor cabin 1 shown in fig. 1 comprises a pressure relief pipe 4, a multi-stage pressure relief assembly, a pressure suppression assembly and a sewage tank 14, wherein the inlet end of the pressure relief pipe 4 is communicated with the interior of the reactor cabin 1; the multi-stage pressure relief assembly is arranged in the pressure relief pipe 4 or on a bypass branch pipe of the pressure relief pipe 4; the pressure-restraining component is communicated with the pressure relief pipe 4; the inlet of the sewage tank 14 is communicated with the bottom of the reactor cabin 1 through a safe drainage pipeline 16, and the outlet of the sewage tank 14 is communicated with a radioactive wastewater treatment system.
In this embodiment, the safety drain pipe 16 is provided with a safety drain valve 15; the safe drainage pipeline 16 is used for draining accumulated water in the reactor cabin 1 into the sewage tank 14 for temporary sealing; the sewage tank 14 is connected with a vacuum-pumping system, and the interior of the sewage tank is designed to be negative pressure, so that the tightness of the tank body is ensured.
Preferably, multistage pressure release subassembly includes relief valve 2 and one-level rupture disk 3, and relief valve 2 installs on bypass branch pipe, and one-level rupture disk 3 is located in the pressure release main pipe, and bypass branch pipe and 4 tie points of pressure release pipe are located the both ends of one-level rupture disk 3 (one-level rupture disk 3 and relief valve 2 arrange side by side). The multistage pressure relief assembly further comprises a second-stage rupture disc 5, the second-stage rupture disc 5 is arranged in the pressure relief pipe 4, and the second-stage rupture disc 5 is located at the downstream position of the connecting point of the flow distribution main pipe and the pressure relief pipe 4; the outlet end of the pressure relief pipe 4 is provided with a filtering module 6, and the outlet end of the pressure relief pipe 4 is communicated with an emergency exhaust system; the opening pressures of the pressure release valve 2, the first-stage rupture disk 3 and the second-stage rupture disk 5 are sequentially increased. After the second-stage rupture disk 5 is opened, steam in the reactor cabin 1 is exhausted from the outlet end of the pressure relief pipe 4 through the second-stage rupture disk 5.
In the embodiment, the pressure release valve 2, the first-stage rupture disk 3 and the second-stage rupture disk 5 are key components of an overpressure protection system of the reactor cabin 1, the first-stage rupture disk 3 is close to the reactor cabin 1, the second-stage rupture disk 5 is far away from the reactor cabin 1, and the two-stage rupture disks are sequentially arranged on the pressure release pipe 4 and work in series; the pressure release valve 2 is arranged on a bypass pipeline of the first-stage rupture disk 3, so that frequent replacement of the disposable rupture disk can be avoided, and the pressure release valve 2 and the first-stage rupture disk 3 work in parallel and simultaneously work in series with the second-stage rupture disk 5; the opening pressures of the pressure release valve 2, the primary rupture disk 3 and the secondary rupture disk 5 are sequentially increased and are respectively used for dealing with small-size coolant leakage accidents, large-size coolant leakage accidents and extreme coolant leakage accidents.
The primary rupture disk 3 and the secondary rupture disk 5 are disposable elements, adopt a reverse bending structure, and have good structural stability, large flow area and good sealing effect; the pressure relief valve 2 can be reused, but the flow area is small. In order to ensure a good sealing effect, the pressure release valves 2, the first-stage rupture discs 3 and the second-stage rupture discs 5 are all configured in groups, each group comprises two rupture discs, and the group configuration can also avoid the influence of accidental opening of the pressure release valves 2 or the rupture discs at the near ends on the reactor cabin 1; the pipeline between two relief valves 2, the pipeline between two one-level rupture discs 3, and the pipeline between two second-level rupture discs 5 are equallyd divide and are do not link to each other with vacuum pumping system, before whole system operation, need carry out the evacuation to the pipeline between two relief valves 2, the pipeline between two one-level rupture discs 3, the pipeline between two second-level rupture discs 5, avoid radioactive substance to leak, eliminate the influence of backpressure.
Preferably, the pressure-suppressing assembly comprises a pressure-suppressing tank 8 and a flow-dividing assembly arranged in the pressure-suppressing tank 8, wherein pressure-suppressing water (room temperature) is arranged in the pressure-suppressing tank 8, the interior of the pressure-suppressing tank 8 is divided into a lower water space and an upper air space by a horizontal plane of the pressure-suppressing water, the water space is communicated with the sewage tank 14 through a drain valve, and the air space is respectively communicated with a purging system and a vacuum-pumping system; the flow dividing assembly comprises a flow divider 7 and a plurality of porous pipes 9 which are mutually parallel and communicated with the flow dividing main pipe; the flow divider 7 is connected with the pressure relief pipe 4, and the connection point of the flow divider and the pressure relief pipe is positioned at the downstream of the connection point of the bypass branch pipe and the pressure relief pipe 4; the perforated pipe 9 is completely submerged in the suppression water of the suppression tank 8.
In the embodiment, the suppression tank 8 is a horizontal tank body, the capacity of the tank body is large enough to simultaneously contain suppression water and condensed water, the suppression water does not fill the whole suppression tank 8, and a gas volume is reserved; before the pressure-restraining tank 8 is put into operation, purging is carried out, vacuumizing is carried out, negative pressure is kept, leakage of radioactive substances is avoided, and the steam release effect is further improved; enough pressure-restraining water (the initial temperature is room temperature) is filled in the pressure-restraining groove 8, so that steam from the flow divider 7 can be completely condensed, the overheating of the initial liquid is eliminated, and the pressure of the discharge end of the pressure-releasing pipe 4 is unchanged.
In this embodiment, the flow divider 7 is used to distribute the steam from the pressure relief pipe 4 evenly into the perforated pipe 9 below; the perforated pipe 9 is provided with a plurality of small holes as air injection holes, and steam enters water through the air injection holes; the gas injection holes form steam nozzles, the diameter of the nozzles is small enough to ensure that steam bubbles are quickly broken in water, and the collapse (condensation) time of the bubbles is short enough; the water level of the gas injection holes should be deep enough to ensure that the steam bubbles are completely condensed before rising to the water surface.
Preferably, the gas space of the pressure-restraining tank 8 is communicated with the top inlet of the steam-water separator 10, the gas outlet of the steam-water separator 10 is communicated with the waste gas treatment system, and the liquid outlet of the steam-water separator 10 is communicated with the sewage tank 14 through a water outlet pipeline; the top of the waste water tank 14 is communicated with an exhaust system or a vacuum pumping system.
Preferably, the water space of the pressure-restraining groove 8 is communicated with an external water replenishing pipeline, and a water replenishing valve 11 is arranged on the water replenishing pipeline.
In this embodiment, since the released steam contains non-condensable gas (e.g., air), the pressure inside the pressure-suppressing tank 8 rises, and after the set value is reached, the gas inside the pressure-suppressing tank 8 needs to be discharged into the steam-water separator 10; the steam-water separator 10 is responsible for separating the gas-liquid mixture from the pressure-restraining tank 8, non-condensable gas is discharged to a radioactive waste gas treatment system, and condensed water is discharged to a sewage tank 14 for temporary storage. The released steam is continuously condensed in the pressure-restraining tank 8, so that the water level rises and the water temperature rises; therefore, the water level and the water temperature in the pressure-suppressing tank 8 are monitored (detected by the liquid level sensor and the temperature sensor), and when the water level or the water temperature reaches a design value, the heated water needs to be drained to the sewage tank 14 in time, and the pressure-suppressing water needs to be replenished.
In the invention, the sewage tank 14 is connected with a vacuum-pumping system, and the interior of the sewage tank is designed to be negative pressure, so that the tightness of the tank body is ensured; the sewage tank 14 is provided with a liquid level sensor and a pressure sensor, and the sewage tank 14 receives the wastewater from the safe drainage pipeline 16, the steam-water separator 10 and the pressure-restraining tank 8 and monitors the water level and the pressure in the sewage tank; when the water level exceeds a set value, discharging the redundant water to a radioactive wastewater treatment system; the sewage tank 14 is connected with an exhaust system, and when the internal pressure of the sewage tank 14 exceeds a set value, the redundant gas at the top is exhausted, so that the internal pressure is ensured to be lower than the set value.
The working principle of the invention is as follows: the reactor cabin 1 is connected with a vacuum pumping system, the initial pressure inside the reactor cabin 1 is negative pressure, and leakage of radioactive substances is avoided; as shown in fig. 2, after a coolant leakage accident occurs, the internal pressure of the reactor cabin 1 rises rapidly, when the pressure in the reactor cabin 1 reaches the opening pressure of the pressure relief valve 2, the pressure relief valve 2 is opened, high-pressure steam in the reactor cabin 1 enters the pressure-suppressing water in the pressure-suppressing tank 8 through the pressure relief pipe 4, the flow divider 7 and the porous pipe 9 in sequence, the steam is completely condensed in the pressure-suppressing water, and the pressure at the tail end of the pressure relief valve 2 is not affected; if the pressure relief valve 2 is opened, the pressure rise in the reactor cabin 1 cannot be effectively inhibited, when the pressure value reaches the opening pressure of the first-stage rupture disk 3, the first-stage rupture disk 3 is opened, and steam with larger flow rate is released into the pressure inhibition groove 8; if the back is opened to one-level rupture disk 3, still can't effectively restrain 1 internal pressure in reactor cabin and rise, after the pressure value reached the opening pressure of second grade rupture disk 5, second grade rupture disk 5 opened, and the emergent exhaust system of releasing after 6 filtration treatment of module is strained to the inside high-pressure steam in reactor cabin 1 avoids the further deterioration of affairs.
Before the pressure-restraining tank 8 starts to work, purging and vacuumizing are carried out, and the interior of the pressure-restraining tank 8 is kept in a negative pressure state; the released steam contains non-condensable gas, which can cause the pressure in the pressure suppression tank 8 to rise, when the pressure value exceeds a set value, the gas-water mixture is discharged into a steam-water separator 10, the gas is discharged into a radioactive waste gas treatment system, and the wastewater is discharged into a sewage tank 14; when the water level or the water temperature of the pressure-suppressed water exceeds a set value, a drain valve is opened to drain water to a sewage tank 14, and then a water supplementing valve 11 is opened to supplement the pressure-suppressed water to a pressure-suppressing tank 8 (the water supplementing valve 11 has a non-return function, so that the backflow of the pressure-suppressed water can be prevented from polluting a water supplementing source); the bottom of the reactor cabin 1 is connected with a sewage tank 14 through a safe drainage pipeline 16, and a safe drainage valve 15 is arranged on the safe drainage pipeline 16; when the water level of the accumulated water in the reactor cabin 1 exceeds a set value, opening the safety drain valve 15 and draining the water to the sewage tank 14; the interior of the sewage tank 14 is in a negative pressure state, and is responsible for temporarily storing the radioactive wastewater, when the internal pressure exceeds a set value, the exhaust valve 13 is opened to exhaust the radioactive wastewater to the exhaust system, and when the internal water level exceeds a set value, the radioactive wastewater is discharged to the radioactive wastewater treatment system.
It should be noted that the above-mentioned embodiments are only preferred embodiments of the present invention, and the present invention is not limited thereto, and although the present invention has been described in detail with reference to the embodiments, it will be apparent to those skilled in the art that modifications can be made to the technical solutions described in the above-mentioned embodiments, or equivalent substitutions of some technical features, but any modifications, equivalents, improvements and the like within the spirit and principle of the present invention shall be included in the protection scope of the present invention.
Claims (8)
1. The overpressure protection system of the reactor cabin is characterized by comprising a pressure relief pipe, a multi-stage pressure relief assembly, a pressure suppression assembly and a sewage tank, wherein the inlet end of the pressure relief pipe is communicated with the interior of the reactor cabin; the multistage pressure relief assembly is arranged in the pressure relief pipe or on a bypass branch pipe of the pressure relief pipe; the pressure-restraining component is communicated with the pressure-relief pipe; an inlet of the sewage tank is communicated with the bottom of the reactor cabin through a safe drainage pipeline, and an outlet of the sewage tank is communicated with the radioactive wastewater treatment system; the multistage pressure relief assembly comprises a pressure relief valve and a first-stage rupture disk, the pressure relief valve is arranged on the bypass branch pipe, the first-stage rupture disk is arranged in the pressure relief main pipe, and a connecting point of the bypass branch pipe and the pressure relief pipe is positioned at two ends of the first-stage rupture disk; the pressure-suppressing assembly comprises a pressure-suppressing groove and a flow-dividing assembly arranged in the pressure-suppressing groove, pressure-suppressing water is filled in the pressure-suppressing groove, the horizontal plane of the pressure-suppressing water divides the interior of the pressure-suppressing groove into a water space at the lower part and an air space at the upper part, the water space is communicated with the sewage tank through a drain valve, and the air space is respectively communicated with a purging system and a vacuum-pumping system; the flow distribution assembly comprises a flow divider and a plurality of porous pipes which are mutually parallel and communicated with the flow distribution main pipe, a plurality of small holes are arranged on the porous pipes to be used as air injection holes, steam enters water through the air injection holes, and the air injection holes form steam nozzles; the flow divider is connected with the pressure relief pipe, and the connection point of the flow divider and the pressure relief pipe is positioned at the downstream of the connection point of the bypass branch pipe and the pressure relief pipe; the porous pipe is completely submerged in the suppression water of the suppression tank; before the pressure-restraining tank is put into operation, purging is carried out, vacuumizing is carried out, and negative pressure is kept.
2. The reactor compartment overpressure protection system of claim 1 wherein said multi-stage pressure relief assembly further comprises a secondary rupture disc, said secondary rupture disc being disposed within the pressure relief tube and being located downstream of the junction of the main flow splitting tube and the pressure relief tube; the opening pressures of the pressure release valve, the first-stage rupture disk and the second-stage rupture disk are sequentially increased; the outlet end of the pressure relief pipe is communicated with an emergency exhaust system.
3. The reactor compartment overpressure protection system of claim 1 wherein the gas space of said surge tank is in communication with the top inlet of a steam-water separator, the gas outlet of which is in communication with the exhaust gas treatment system, the liquid outlet of which is in communication with the waste tank via an outlet conduit; the top of the sewage tank is communicated with an exhaust system or a vacuum-pumping system.
4. The reactor cabin overpressure protection system of claim 1, wherein the water space of said pressure-suppressing tank is communicated with an external water-replenishing pipeline, and a water-replenishing valve is disposed on the water-replenishing pipeline.
5. The reactor cabin overpressure protection system of claim 1 wherein the tank is provided with a level sensor and a pressure sensor.
6. The reactor compartment overpressure protection system of claim 2 wherein the pressure relief valves, the primary rupture discs and the secondary rupture discs are all configured in groups of two; and the pipeline between the two pressure release valves, the pipeline between the two first-stage rupture discs and the pipeline between the two second-stage rupture discs are respectively connected with a vacuum pumping system.
7. The reactor compartment overpressure protection system of claim 2 wherein an outlet end of said pressure relief tube is provided with a filter module.
8. The reactor compartment overpressure protection system of claim 1 wherein the surge tank houses a level sensor, a temperature sensor, and a pressure sensor.
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| CN201911017132.4A CN110648770B (en) | 2019-10-24 | 2019-10-24 | Overpressure protection system for reactor cabin |
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| CN201911017132.4A CN110648770B (en) | 2019-10-24 | 2019-10-24 | Overpressure protection system for reactor cabin |
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| CN110648770B true CN110648770B (en) | 2023-02-03 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111508623B (en) * | 2020-04-29 | 2022-07-15 | 中国核动力研究设计院 | Overpressure protection device for pressure-bearing containment vessel for ship and application of overpressure protection device |
| CN112473584A (en) * | 2020-11-13 | 2021-03-12 | 中广核工程有限公司 | Passive safety protection system of supercritical water oxidation reactor |
| CN112856004A (en) * | 2020-12-30 | 2021-05-28 | 江苏安泰安全技术有限公司 | Proportional control safety valve pressure relief method and device |
| CN115193307B (en) * | 2022-06-06 | 2023-08-15 | 中南大学湘雅医院 | Be used for chest internal medicine agitating unit |
| CN115331538A (en) * | 2022-08-29 | 2022-11-11 | 中国舰船研究设计中心 | Steam generator secondary side boundary simulation device for water supply system test |
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