CN112053792B - Nuclear power plant post-accident containment heat exporting system - Google Patents
Nuclear power plant post-accident containment heat exporting system Download PDFInfo
- Publication number
- CN112053792B CN112053792B CN202010896533.8A CN202010896533A CN112053792B CN 112053792 B CN112053792 B CN 112053792B CN 202010896533 A CN202010896533 A CN 202010896533A CN 112053792 B CN112053792 B CN 112053792B
- Authority
- CN
- China
- Prior art keywords
- containment
- humidifying water
- shell
- heat
- water tank
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/02—Arrangements of auxiliary equipment
-
- 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
-
- 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)
Abstract
The invention provides a heat export system of a containment vessel after a nuclear power plant accident, wherein the containment vessel comprises an inner shell, an outer shell and a base, ventilation channels are formed between the inner shell and the outer shell of the containment vessel and between the outer shell of the containment vessel and the base of the containment vessel, and the heat export system comprises: the humidifying water tanks are arranged on the safety shell base at the bottom of the ventilation channel, the tops of the humidifying water tanks are opened, and water is contained in the humidifying water tanks; and a plurality of groups of immersed ultrasonic oscillators, wherein each group of immersed ultrasonic oscillator corresponds to one humidifying water pool, is arranged in the corresponding humidifying water pool and is used for atomizing water in the corresponding humidifying water pool. According to the heat exporting system, the micro liquid drops generated by the immersed ultrasonic oscillator in the natural ventilation channel are thrown and directly evaporated, so that the containment vessel obtains higher heat exporting power.
Description
Technical Field
The invention relates to the technical field of nuclear power plants, in particular to a containment heat exporting system after a nuclear power plant accident.
Background
The closed containment is an important barrier for preventing radioactive substances from leaking out when an accident occurs in a nuclear power plant. Normally, the containment vessel will be isolated after an accident to become an enclosed space, and the sharply elevated temperatures and pressures are all borne by the containment structure. The design requires the containment vessel to have larger free volume and shell thickness, and also requires a matched containment vessel pressure reduction and heat conduction system to have higher performance after an accident.
After an accident, the core problem of the closed containment vessel of the nuclear power plant is the derivation of the waste heat of the reactor, and if a waste heat derivation mechanism is lost, the temperature and the pressure in the containment vessel can continuously rise until the containment vessel is broken.
For the problem of residual heat removal of the reactor after an accident, some heat removal systems are provided in the related art. Particularly, the second generation nuclear power technology (M310) and the European third generation nuclear power technology (EPR) mainly adopt active means; the third generation nuclear power system is provided with a passive containment heat removal system (PCCS), such as: ACP1000-PCS, AP600&1000-PCS, ABWRII-PCCS, AHWR-PCCS, ESBWR-PCCS, SWR1000-PCCS, WWER640-PCCS, WWER1000-PCCS, and the like. Typical passive containment heat removal systems involve patents including: PASSIVE CONTAINMENT COOLING SYSTEM filed by US West House, 1991 (US 5049353); U.S. Pat. No. 2,1962 entitled SAFETY EQUIPMENT FORNUCLEAR POWER-REACTOR PLANTS (US 31684454); PASSIVE CONTAINMENT COOLINGSYSTEM (US 5282230) applied by GE corporation, 1994; PRESSURESUPPRESSION CONTAINMENT SYSTEM (US 5295168) filed by GE, 1994; water infusion monomer POOL OF BOLING WATER REACTOR (US 5499278) applied by GE corporation in 1996; MODIFIED PASSIVECONTAINMENT COOLING SYSTEM FOR NUCLEAR REACTOR (US 6069930) applied by GE corporation in 2000. The technical scheme of the patent does not adopt the technologies of ultrasonic atomization, atomization humidification, direct evaporative cooling of air and the like. After 2000 years, the use of ultrasonic atomization direct evaporative cooling technology in the whole industry is increasing, and particularly relates to a cooling process in a machining process, such as: ultrasonic cutting blade with cooking (US 6379371); electronic component cooling, such as: coating of electronics and high density power distribution systems by fine-mix coating (US 6955063), ultrasonic cutting blade with continuous liquid reduction (US 9387005); thermal power system cooling, such as: atomizing and cooling mechanism (CN 201610822806.8), atomizing device and oxygen cabin cooling water atomizing system (CN 201820873905.3), a split air conditioner based on condensed water atomizing and cooling (CN 201710471612.2), ultrasonic water atomization system for Gas turbine aeration and wet compression (US 9387005), apparatus, systems, and methods to apply aeration and wet compression for organic thermal management (US 10012141), gas turbine aeration system using Ultrasonic aeration, gasification co-aeration method and wet compression system (EP 25735a945, US 413654942); chemical cooling processes, such as: ultrasonic atomization continuous spray coating process (CN 201611006764.7), chemical vapor deposition reactor with preheating, reaction, and continuous zones (US 9816185), etc. However, the heat removal systems involved in these technologies have problems of more or less complicated structure, high energy consumption, poor reliability, and low heat removal power.
Disclosure of Invention
The present invention has been made to solve, at least in part, the technical problems occurring in the prior art.
The technical scheme adopted for solving the technical problem of the invention is as follows:
the invention provides a heat export system of a containment vessel after a nuclear power plant accident, wherein the containment vessel comprises an inner shell, an outer shell and a base, and ventilation channels are formed between the inner shell of the containment vessel and the outer shell of the containment vessel and between the outer shell of the containment vessel and the base of the containment vessel, and the heat export system is characterized by comprising:
the humidifying water tanks are arranged on the safety shell base at the bottom of the ventilation channel, the tops of the humidifying water tanks are opened, and water is contained in the humidifying water tanks; and the number of the first and second groups,
and each group of immersed ultrasonic oscillators corresponds to one humidifying water pool and is arranged in the corresponding humidifying water pool for atomizing water in the corresponding humidifying water pool.
Optionally, the diameter of the immersed ultrasonic oscillator atomized liquid droplets is 1-5 μm.
Optionally, a power supply line of the submerged ultrasonic oscillator is connected with a 1E-level direct current power supply of a nuclear power plant, an emergency diesel generator set or a mobile diesel generator.
Optionally, the water level of the humidification water tank is lower than the heat conduction interface of the inner shell of the containment.
Optionally, the heat deriving system further comprises: each humidifying water tank preheater corresponds to one humidifying water tank and is arranged in the corresponding humidifying water tank; the humidifying water tank preheater is used for raising the temperature of the water body in the corresponding humidifying water tank to a preset temperature.
Optionally, the maximum value of the preset temperature is 50 ℃.
Optionally, the humidifying water tank pre-heater is of an electric heating type.
Optionally, the humidifying water pool pre-heater is of a direct heating type and is connected with the heat transfer body through a direct heating path; the heat transfer body is a containment shell or a heat pipe.
Optionally, the heat deriving system further comprises: a spray head of the containment inner shell spray system is positioned above the containment inner shell; and non-evaporated spray water sprayed by the containment shell spraying system is injected into the humidifying water pool through a spray water collecting path.
Optionally, the inner shell of the containment is a steel inner shell; the containment shell is a concrete shell.
Has the advantages that:
according to the invention, the temperature of the inner shell of the containment vessel is continuously raised after an accident, the ventilation channel is heated and a chimney effect is formed, meanwhile, the water in the humidification water tank is ultrasonically atomized into micro droplets by the immersed ultrasonic oscillator, and the micro droplets are carried into the ventilation channel by the natural ventilation clamp.
In addition, the natural ventilation channel is cooled through the direct evaporation of the micro-droplets, so that the coolant is completely changed in phase, and the highest coolant use efficiency is achieved; the immersed ultrasonic oscillator is used for ultrasonic atomization to form micro-droplets, and no rotating part is used, so that the system has higher reliability; the micro-droplets are entrained and lifted by natural ventilation in the ventilation channel without the aid of active equipment, so that the system has lower energy consumption and higher reliability.
Drawings
Fig. 1 is a schematic structural diagram of a containment heat export system after a nuclear power plant accident according to an embodiment of the present invention.
In the figure: 1-a steel inner shell; 2-concrete shell; 3, humidifying a water tank; 4-an immersed ultrasonic oscillator; 41-immersed ultrasonic oscillator power supply line; 44-a humidifying pool preheater; 5-a safety housing base; 7-ventilation channel inlet; 8-vent channel outlet; 9-a ventilation channel rise zone; 10-shell interior space; 11-a ventilation channel diffusion zone; 12-steel shell heat-removal interface; 13-a spray head; 14-spray water supply line; 15-spraying water supply tank; 16-spray water collection path; 17-direct heating path.
Detailed Description
In order to make the technical solutions of the present invention better understood, the present invention is further described in detail below with reference to the accompanying drawings and examples.
In the description of the present invention, it is to be understood that the orientations and positional relationships indicated by the various positional terms are based on the orientations and positional relationships shown in the drawings only for the convenience of describing the present invention and for the simplicity of description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and thus, should not be construed as limiting the present invention.
As shown in fig. 1, the containment comprises an inner shell, an outer shell and a base, wherein the inner shell encloses a shell space 10, the inner shell is placed on the base 5, and the outer shell is sleeved on the inner shell. Generally, the inner shell of the containment vessel adopts a steel inner shell 1, the outer shell of the containment vessel adopts a concrete outer shell 2, and ventilation channels are formed between the steel inner shell 1 and the concrete outer shell 2 and between the concrete outer shell 2 and a base 5 of the containment vessel, wherein a vertical middle section and a top of the ventilation channel are formed between the steel inner shell 1 and the concrete outer shell 2, and a bottom of the ventilation channel is formed between the concrete outer shell 2 and the base 5 of the containment vessel. For the whole ventilation channel, the ventilation channel inlet 7 is positioned at the bottom of the ventilation channel, the ventilation channel ascending region 9 is positioned in the vertical middle section of the ventilation channel, the ventilation channel diffusion region 11 is positioned at the top of the ventilation channel, and the ventilation channel outlet 8 is arranged at the top of the concrete shell 2 and is communicated with the top of the ventilation channel.
After an accident, the temperature and the pressure in the steel inner shell 1 will continuously rise, and heat of the steel inner shell 1 needs to be conducted out. As shown in fig. 1, the heat removal system includes: a plurality of humidification water tanks 3 and a plurality of groups of immersed ultrasonic oscillators 4, each group of immersed ultrasonic oscillators includes a plurality of immersed ultrasonic oscillators 4.
The humidifying pool 3 is arranged on a containment base 5 at the bottom of the ventilation channel, and the concrete shell 2 at the position is arranged opposite to the containment base 5; the humidifying water tank 3 is opened at the top and contains water therein. Each group of immersed ultrasonic oscillators 4 corresponds to one humidification water tank 3, is arranged in the corresponding humidification water tank 3 and is used for atomizing water in the corresponding humidification water tank 3. In other words, a set of submerged ultrasonic oscillators 4 is provided in each humidification water tank 3.
Although only two humidifying water pools 3 and two corresponding sets of submerged ultrasonic oscillators 4 are shown in fig. 1, and each set of submerged ultrasonic oscillators includes three submerged ultrasonic oscillators 4, this is merely an exemplary structure provided for illustrating the inventive principle, the structure of the present invention is not limited thereto, and a greater or lesser number of humidifying water pools and submerged ultrasonic oscillators are within the protection scope of the present invention, and a person skilled in the art can set the number of humidifying water pools and their corresponding submerged ultrasonic oscillators according to actual conditions, and adjust the respective setting positions within a given range.
In the embodiment of the invention, the temperature of the steel inner shell is continuously raised after an accident, the ventilation channel is heated and a chimney effect is formed, meanwhile, the water in the humidification water tank is ultrasonically atomized into micro droplets by the immersed ultrasonic oscillator, and the micro droplets are clamped into the ventilation channel by natural ventilation.
In addition, the natural ventilation channel is cooled through the direct evaporation of the micro-droplets, so that the coolant is completely changed in phase, and the highest coolant use efficiency is achieved; the immersed ultrasonic oscillator is used for ultrasonic atomization to form micro-droplets, and no rotating part is used, so that the system has higher reliability; the micro-droplets are entrained and lifted by natural ventilation in the ventilation channel without the aid of active equipment, so that the system has lower energy consumption and higher reliability.
In some embodiments, the diameter of the atomized droplets of the submerged ultrasonic oscillator 4 is 1 to 5 μm.
Wherein the size of the diameter of the atomized liquid droplets can be adjusted by adjusting the vibration frequency of the submerged ultrasonic oscillator, thereby obtaining atomized liquid droplets of a desired diameter.
Because the diameter of the atomized liquid drop is small, the atomized liquid drop can be directly entrained by natural ventilation and can be evaporated to absorb heat.
As shown in fig. 1, the submerged ultrasonic oscillator 4 provides post-accident power input by a submerged ultrasonic oscillator power supply line 41. In some embodiments, the submerged ultrasonic oscillator power supply line 41 is connected to a class 1E dc power source of a nuclear power plant, an emergency diesel generator set, or a mobile diesel generator.
In some embodiments, the water elevation of the humidification water tank 3 is lower than the heat-conducting interface (steel shell heat-conducting interface 12) of the inner containment shell, so that atomized liquid droplets released by the humidification water tank can more comprehensively and effectively cool the inner steel shell 1.
As shown in fig. 1, the heat removal system further includes: a plurality of humidified water tank preheaters 44.
Each of the humidification water tank preheaters 44 corresponds to one of the humidification water tanks 3 and is disposed in the corresponding humidification water tank 3. The humidifying water tank pre-heater 44 is used for raising the temperature of the water body in the corresponding humidifying water tank 3 to a preset temperature.
Because the humidifying water tank preheater 44 is arranged in the humidifying water tank 3 to heat the water body in the humidifying water tank 3, so that the temperature of the water body is raised, the atomization effect can be obviously enhanced, more heat can be absorbed, and the input power required by ultrasonic atomization of the immersed ultrasonic oscillator is correspondingly reduced.
The maximum limit value of the preset temperature is 50 ℃, namely the maximum humidifying water tank water supplement preheater 44 can raise the temperature of the water body in the humidifying water tank 3 to 50 ℃ so as to avoid the failure of the immersed ultrasonic oscillator 4.
In some embodiments, the humidifying water tank pre-heater 44 is of an electrically heated type and can be powered by a submerged ultrasonic oscillator power supply line 41.
By energizing the humidification water tank preheater 44, the water in the humidification water tank 3 can be heated; and, the temperature of the water in the humidification water tank 3 can be adjusted by adjusting the power of the humidification water tank preheater 44.
In other embodiments, the humidification water tank preheater 44 is of the direct heating type and is connected to the heat transfer body by a direct heating path 17; the heat transfer body is heat transfer equipment such as a containment inner shell (steel inner shell 1) or a heat pipe.
After the temperature of the steel inner shell 1 rises, the temperature of the steel shell heat-conducting interface 12 is higher, and the humidifying water pool preheater 44 is connected with the steel inner shell 1 through the direct heating path 17, so that the water body in the humidifying water pool 3 can be further heated.
As shown in fig. 1, the heat removal system further includes: and (4) a spraying system (steel shell spraying system) for the inner shell of the containment. The steel-shelled spraying system comprises: a plurality of spray heads 13, a spray water supply line 14 and a spray water supply tank 15. Wherein, the spray head 13 is arranged above the steel inner shell 1, and the spray head 13 is arranged on a spray water supply pipeline 14; the spray water supply line 14 is also connected to a spray water supply tank 15.
The non-evaporated shower water sprayed from the steel shell sprinkler system is injected into the humidification water tank 3 through the shower water collection path 16, thereby recovering the non-evaporated shower water.
In summary, according to the containment heat exporting system after the nuclear power plant accident, the humidifying water tank is arranged on the containment base at the bottom of the ventilation channel, and the immersed ultrasonic oscillator is arranged in the humidifying water tank, so that the containment obtains larger heat exporting power through the throwing in and direct evaporation of micro-droplets generated by the immersed ultrasonic oscillator in the natural ventilation channel.
In particular, the heat deriving system has the following advantages:
1) Micro liquid drops generated by the immersed ultrasonic oscillator directly evaporate to cool the natural ventilation channel, the coolant completely changes phase, and the highest coolant use efficiency is achieved;
2) The generation of micro-droplets is based on an ultrasonic oscillator without a rotating part, so that the system has higher reliability;
3) The micro liquid drops are entrained and lifted by natural ventilation in the ventilation channel without the aid of active equipment, so that the system has lower energy consumption and higher reliability;
4) The system has lower power, less required coolant and lower dependence on emergency support, and can be put into the accident link earlier.
It will be understood that the above embodiments are merely exemplary embodiments adopted to illustrate the principles of the present invention, and the present invention is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (9)
1. The utility model provides a containment heat derivation system after nuclear power plant accident, the containment includes inner shell, shell and base, and between containment inner shell and the containment shell to and be formed with ventilation channel between containment shell and the containment base, its characterized in that, the heat derivation system includes:
the humidifying water tanks are arranged on the safety shell base at the bottom of the ventilation channel, the tops of the humidifying water tanks are open, and water is contained in the humidifying water tanks; and (c) a second step of,
the system comprises a plurality of groups of immersed ultrasonic oscillators, wherein each group of immersed ultrasonic oscillators corresponds to a humidifying water pool, is arranged in the corresponding humidifying water pool and is used for atomizing water in the corresponding humidifying water pool;
further comprising: each humidifying water tank preheater corresponds to one humidifying water tank and is arranged in the corresponding humidifying water tank; the humidifying water tank preheater is used for raising the temperature of the water body in the corresponding humidifying water tank to a preset temperature.
2. The heat removal system of claim 1, wherein the submerged ultrasonic oscillator atomizes droplets having a diameter of 1-5 μm.
3. The heat removal system of claim 1, wherein the power supply line of the submerged ultrasonic oscillator is connected to a nuclear power plant class 1E dc power supply, an emergency diesel generator set, or a mobile diesel generator.
4. The heat removal system of claim 1, wherein the level of the body of water in the humidification pool is below the inner containment shell heat removal interface.
5. The heat removal system of claim 1, wherein the preset temperature has a maximum value of 50 ℃.
6. The heat removal system of claim 1, wherein the humidifying water pool preheater is of the electric heating type.
7. The heat removal system of claim 1, wherein the humidifying water tank pre-heater is of a direct heating type and is connected to the heat transfer body through a direct heating path; the heat transfer body is a containment shell or a heat pipe.
8. The heat removal system of claim 1, further comprising: a spray head of the containment inner shell spray system is positioned above the containment inner shell; and non-evaporated spray water sprayed by the containment shell spraying system is injected into the humidifying water pool through a spray water collecting path.
9. The heat removal system of claim 1, wherein the inner containment shell is a steel inner shell; the containment shell is made of concrete.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010896533.8A CN112053792B (en) | 2020-08-31 | 2020-08-31 | Nuclear power plant post-accident containment heat exporting system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010896533.8A CN112053792B (en) | 2020-08-31 | 2020-08-31 | Nuclear power plant post-accident containment heat exporting system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112053792A CN112053792A (en) | 2020-12-08 |
| CN112053792B true CN112053792B (en) | 2023-02-17 |
Family
ID=73607376
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010896533.8A Active CN112053792B (en) | 2020-08-31 | 2020-08-31 | Nuclear power plant post-accident containment heat exporting system |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112053792B (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013104816A (en) * | 2011-11-15 | 2013-05-30 | Toshiba Corp | Device and method for cooling reactor containment vessel |
| CN203931516U (en) * | 2014-06-19 | 2014-11-05 | 华北电力大学 | A kind of Passive containment cooling system of applying phase-change heat transfer |
| CN104217773A (en) * | 2014-07-30 | 2014-12-17 | 中国核电工程有限公司 | Nuclear power plant steel safe containment vessel heat-conductive device |
| CN106128526A (en) * | 2016-08-10 | 2016-11-16 | 长江勘测规划设计研究有限责任公司 | A kind of ellipsoid formula underground nuclear power station containment system |
| CN111599498A (en) * | 2020-04-14 | 2020-08-28 | 中国核电工程有限公司 | Passive containment air-water long-term cooling system |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| TWI251658B (en) * | 2004-12-16 | 2006-03-21 | Ind Tech Res Inst | Ultrasonic atomizing cooling apparatus |
-
2020
- 2020-08-31 CN CN202010896533.8A patent/CN112053792B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013104816A (en) * | 2011-11-15 | 2013-05-30 | Toshiba Corp | Device and method for cooling reactor containment vessel |
| CN203931516U (en) * | 2014-06-19 | 2014-11-05 | 华北电力大学 | A kind of Passive containment cooling system of applying phase-change heat transfer |
| CN104217773A (en) * | 2014-07-30 | 2014-12-17 | 中国核电工程有限公司 | Nuclear power plant steel safe containment vessel heat-conductive device |
| CN106128526A (en) * | 2016-08-10 | 2016-11-16 | 长江勘测规划设计研究有限责任公司 | A kind of ellipsoid formula underground nuclear power station containment system |
| CN111599498A (en) * | 2020-04-14 | 2020-08-28 | 中国核电工程有限公司 | Passive containment air-water long-term cooling system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN112053792A (en) | 2020-12-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US20180350472A1 (en) | Passive safe cooling system | |
| RU2515496C2 (en) | System and method of steam generation by high-temperature gas-cooled reactor | |
| CN206040826U (en) | A thermal management system for high altitude unmanned aerial vehicle fuel cell module | |
| KR20150039815A (en) | Containment protection system for a nuclear facility and associated operating method | |
| CN112201371B (en) | Reactor internal melt retention system adopting spray cooling | |
| CN112071452B (en) | Nuclear power plant post-accident containment heat exporting system | |
| CN112053792B (en) | Nuclear power plant post-accident containment heat exporting system | |
| CN105551541B (en) | Reactor core melt grouping trapping and cooling system | |
| RU2695128C1 (en) | Nuclear reactor housing cooling method in case of severe accident and device for its implementation | |
| CN201932925U (en) | Atomizing and humidifying steam generating tower | |
| CN206881508U (en) | A kind of safety-type catalysis oxidation VOCs controlling devices of temperature control | |
| CN100481270C (en) | High power water boiler type solution nuclear reactor gas loop | |
| CN210885391U (en) | Small split solar electrostatic atomization seawater desalination device | |
| RU2695129C1 (en) | Nuclear reactor housing cooling method in case of severe accident and device for its implementation | |
| WO1999061397A2 (en) | Water gas shift reactor and heat exchanger | |
| CN209447555U (en) | A kind of Passive containment cooling system | |
| CN112762750A (en) | Vaporization cooling circuit and calculation board waste heat recovery utilize system | |
| CN212269523U (en) | Dividing wall type deaerating device with horizontal deaerating head | |
| KR100238459B1 (en) | Passive cooling system for concrete containment vessel of pressurized water reactors | |
| CN214653629U (en) | Mixed heater for methanol-water reforming hydrogen production | |
| JPS62131101A (en) | Steam generator | |
| JP7261403B2 (en) | Spray type reheating steam reactor and power generation equipment using it | |
| CN212450727U (en) | Dividing wall type deaerating device with vertical deaerating head | |
| CN216482448U (en) | Vaporization cooling circuit and calculation board waste heat recovery utilize system | |
| CN217881586U (en) | Fuel cell test bench gas humidification tank |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |