CN202855316U - Containment cooling system for PWR (pressurized water reactor) nuclear power plant - Google Patents
Containment cooling system for PWR (pressurized water reactor) nuclear power plant Download PDFInfo
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- CN202855316U CN202855316U CN2012204610667U CN201220461066U CN202855316U CN 202855316 U CN202855316 U CN 202855316U CN 2012204610667 U CN2012204610667 U CN 2012204610667U CN 201220461066 U CN201220461066 U CN 201220461066U CN 202855316 U CN202855316 U CN 202855316U
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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
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Abstract
The utility model relates to a containment cooling system for a PWR (pressurized water reactor) nuclear power plant. The containment cooling system comprises a containment, a pressure vessel, a steam generator, a pressure stabilizer, a refueling water tank, a cooling system water tank, a first heat exchanger and a second heat exchanger, wherein the pressure vessel is arranged in the containment, the steam generator is connected with the pressure vessel, the pressure stabilizer is connected with the pressure vessel and the steam generator, the refueling water tank is arranged in the containment, the cooling system water tank is arranged at the periphery of the containment, and the first heat exchanger and the second heat exchanger are arranged in the cooling system water tank; a first inlet pipe of the first heat exchanger is communicated with an inner space of the containment, and a first outlet pipe of the first heat exchanger is communicated with the refueling water tank; and a second inlet pipe of the second heat exchanger is communicated with the pressure stabilizer, and a second outlet pipe of the second heat exchanger is communicated with the pressure vessel. The capacity of directly discharging heat of the power plant outside the containment is improved by adopting the first heat exchanger and the second exchanger for discharging heating load in the containment and the pressure vessel and the cooling system water tank for directly discharging heat outside the containment, and further the safety and reliability of the nuclear power plant are improved.
Description
Technical field
The utility model relates to PWR nuclear power plant, more particularly, relates to a kind of containment cooling system that can be used in the PWR nuclear power plant.
Background technology
Improve constantly the construction of the nuclear power station important energy source guarantee that becomes national development gradually along with the security of the ripe nuclear power station of technology.
In more existing PWR nuclear power plants, adopt Passive containment cooling system, its containment is double layer design, the containment skin is shielding case, is xoncrete structure; Internal layer is steel containment vessel, and the Internal architecture thing is in metal containment.
, as heat transfer interface air is introduced from outer shielding case entrance with steel containment vessel, arrived the bottom by the external rings corridor, turn to 180 degree in air baffle bottom, enter the inner loop corridor, upwards flow along the containment inwall again.Exist because inner loop corridor air is heated with water vapor, cause inner and outer ring corridor atmospheric density poor, form the natural convection of air, air is finally discharged from shielding case top chimney.
Further, be provided with the chilled water container at the containment top, water relies on gravity to dirty in the case, forms water membrane on metal containment arc top and the shell wall outside.When containment internal pressure or excess Temperature, system opens automatically.By the water film evaporation of metal containment outside and the heat in the natural convection air derivation containment, reduce the pressure of containment, guarantee that containment is not damaged.
Yet there is following shortcoming at least in the Passive containment cooling system of this structure:
1), carry huge water container (2864m) at the containment top, the extreme events such as strong earthquakes, Hai Xiao, wind spout probably cause structural failure and lose security function, and reliability, the security of nuclear power plant are low;
2), rely on the non-active natural convection of steel containment vessel extraneous air and water film evaporation carries out heat extraction, the heat removal capacity of this design is verified so far fully; Can contain under the emergency conditions that pressure peak is also verified in allowed limits fully.
The utility model content
The technical problems to be solved in the utility model is, provides a kind of and can effectively derive heat in pressure vessel and the containment to guarantee the PWR nuclear power plant containment cooling system of containment integrity.
The technical scheme that its technical matters that solves the utility model adopts is: construct a kind of PWR nuclear power plant containment cooling system, comprise containment, be provided with pressure vessel, the steam generator that is connected with pressure vessel in described containment, be connected to the voltage stabilizer between described pressure vessel and the steam generator and be arranged on material-changing water tank in the described containment; Described pressure vessel also is provided with the direct safety injection pipeline;
Described PWR nuclear power plant containment cooling system comprises the cooling system water tank that is arranged on described containment periphery, is arranged on First Heat Exchanger and the second heat interchanger in the described cooling system water tank;
The first inlet tube of described First Heat Exchanger is connected with space in the described containment, and the first outlet of described First Heat Exchanger is connected with described material-changing water tank;
The second inlet tube of described the second heat interchanger is connected with described voltage stabilizer, and the second outlet of described the second heat interchanger is connected with described pressure vessel.
Preferably, in this PWR nuclear power plant containment cooling system, described the first inlet tube is communicated with the upper space of described containment, and connecting tube is provided with by-pass valve control;
Described the first outlet is communicated with the bottom of described material-changing water tank, and connecting tube is provided with by-pass valve control.
Preferably, in this PWR nuclear power plant containment cooling system, described the second inlet tube is connected with described voltage stabilizer top, and connecting tube is provided with by-pass valve control;
Described the second outlet is connected with described direct safety injection pipeline, and connecting tube is provided with by-pass valve control.
Preferably, in this PWR nuclear power plant containment cooling system, the periphery of described containment also is provided with shielding case, is formed with the air ring corridor between described shielding case and the described containment;
The top of described shielding case is provided with air intake; The top, the outside of described containment is provided with air out; Described air intake and air out are communicated with described air ring corridor.
Preferably, in this PWR nuclear power plant containment cooling system, described shielding case is the concrete shield shell; Described containment is steel containment vessel.
Preferably, in this PWR nuclear power plant containment cooling system, in described air ring corridor, be provided with from top to down the air baffle, described air baffle is separated into external rings corridor and inner loop corridor with described air ring corridor, and described air baffle forms the baffling space that is communicated with described external rings corridor and inner loop corridor with the bottom of described air ring corridor.
Preferably, in this PWR nuclear power plant containment cooling system, described PWR nuclear power plant containment cooling system also comprises constrain pond; The inlet pipe in described constrain pond is communicated with the upper space of described containment.
Preferably, in this PWR nuclear power plant containment cooling system, described constrain pond is arranged on the containment periphery.
Preferably, in this PWR nuclear power plant containment cooling system, described constrain pond is airtight constrain pond, and the inlet pipe in described constrain pond is provided with the normally open valve door.
Preferably, in this PWR nuclear power plant containment cooling system, described cooling system water tank and pressure vessel are arranged on the containment pedestal, and the absolute altitude of cooling system water tank is higher than the absolute altitude of described pressure vessel.
Enforcement the utlity model has following beneficial effect: discharge in the containment and the thermal load in the pressure vessel by First Heat Exchanger and the second heat interchanger, and heat directly is expelled to the outer cooling system water tank of containment, thereby strengthened the ability that power plant's heat is directly discharged outside containment, improved security, the reliability of nuclear power plant.
In addition, as the short term thermal trap, collect fouling gas by constrain pond, reduce the fouling gas concentration in the containment, promote the function of condensation heat extraction, and can prevent and treat the generation of hydrogen explosion.
Description of drawings
The utility model is described in further detail below in conjunction with drawings and Examples, in the accompanying drawing:
Fig. 1 is the schematic diagram of an embodiment of the utility model PWR nuclear power plant containment cooling system.
Embodiment
As shown in Figure 1, be an embodiment of PWR nuclear power plant containment cooling system of the present utility model, comprise containment 14, pressure vessel 1, steam generator 2, voltage stabilizer 3, material-changing water tank 8, Core makeup tank 5, peace notes case 6, cooling system water tank 10, First Heat Exchanger 11, the second heat interchanger 12, afterheat heat exchanger 9 etc.
This containment 14 is installed on the concrete containment pedestal, can adopt steel containment vessel, is beneficial to the heat in the containment 14 is outwards dispersed by modes such as natural convections.
This pressure vessel 1, steam generator 2, voltage stabilizer 3, material-changing water tank 8, Core makeup tank 5, peace notes case 6 etc. can be installed in the containment 14.Steam generator 2 is connected with pressure vessel 1, and is provided with main pump 4 between steam generator 2 and pressure vessel 1, and voltage stabilizer 3 is connected between pressure vessel 1 and the steam generator 2.
This pressure vessel 1 is provided with direct injection pipeline 7, and under accident conditions, Core makeup tank 5, peace are annotated case 6 and can by directly injecting pipeline 7 to pressure vessel 1 interior injection cooling liquid, the reactor core assembly in the pressure vessel 1 be cooled off.
As shown in the figure, cooling system water tank 10 is arranged on containment 14 peripheries, in the present embodiment, this cooling system water tank 10 is directly installed on the containment pedestal, thereby can resist the structural failure that the extreme events such as strong earthquakes, Hai Xiao, wind spout probably cause, improve Security of the system, reliability.And the absolute altitude of this cooling system water tank 10 can be higher than the absolute altitude of pressure vessel 1.
This First Heat Exchanger 11 and the second heat interchanger 12 are arranged in the cooling system water tank 10, utilize cooling system water tank 10 to carry out heat interchange.Upper space in the first inlet tube of this First Heat Exchanger 11 and the containment 14 is connected, and the first outlet is connected with material-changing water tank 8.This first outlet can stretch into built-in material-changing water tank 8 bottoms of containment 14.In the accident middle and later periods, containment 14 interior water vapours enter First Heat Exchanger 11 heat exchange by the first inlet tube, in cooling system water tank 10, carry out condensing heat-exchange, cooled fluid relies on gravity to enter the built-in material-changing water tank 8 of containment 14, then can again enter reactor core by the direct injection of material-changing water tank, carry out the function of Core cooling.
The second inlet tube of this second heat interchanger 12 is connected with voltage stabilizer 3, and the second outlet is connected with pressure vessel 1.In the present embodiment, the second inlet tube links to each other with voltage stabilizer 3 tops, and the second outlet is connected to direct injection pipeline 7.Fluid from voltage stabilizer 3 enters into the second heat interchanger 12 by the second inlet tube, and with heat transferred cooling system water tank 10, cooled cryogen enters direct injection pipeline 7, then enters reactor core, is reused for the cooling reactor core.
The natural circulation cooling passage that forms in First Heat Exchanger 11 and the second heat interchanger 12 is not only carried out the function that waste heat is discharged, and also plays the function of active reduction of blood pressure in high-speed early stage in accident.
Understandable, on the first inlet tube, the first outlet, the second inlet tube and the second outlet, by-pass valve control can be set, with devoting oneself to work of control First Heat Exchanger 11 and the second heat interchanger 12.
Further, also be provided with shielding case 16 in the periphery of containment 14, this shielding case 16 can adopt the concrete shield shell, is set directly on the containment pedestal.Between shielding case 16 and containment 14, be formed with the air ring corridor, utilize natural convection air to take away the heat of containment 14.
In order better to utilize cross-ventilation, in the air ring corridor, be provided with from top to down air baffle 15, the air ring corridor is separated into external rings corridor and inner loop corridor, and in the bottom formation baffling space of gas baffle 15 with the air ring corridor, and be communicated with external rings corridor and inner loop corridor, so that air can be turned in the baffling space.
Air is introduced from the air intake on outer shielding case 16 tops, arrive the bottom by the external rings corridor, turn to 180 degree in air baffle 15 bottoms, enter the inner loop corridor, upwards flow along containment 14 inwalls again, as heat transfer interface, derive heat containment 14 in by natural convection air with the outside surface of containment 14, reduce the pressure of containment 14, then discharge by the air out of containment 14 outside tops.
Further, these containment 14 peripheries also are provided with constrain pond 13, and the inlet pipe in this constrain pond 13 is communicated with the upper space of containment 14.In the present embodiment, this constrain pond 13 can have identical resistance to compression shockproof requirements with containment 14 for being arranged on the airtight constrain pond 13 on the containment pedestal, is essentially the part of containment 14.
And the inlet pipe in constrain pond 13 arranges the normally open valve door, boosts in the containment 14 after the accident, produces pressure reduction between containment 14 and the constrain pond 13, impels the atmosphere in containment 14 internal upper part spaces to enter below the 13 interior liquid levels of constrain pond by inlet pipe.At this moment, carry out condensation by the 13 pairs of water vapor that enter in constrain pond, and fouling gas upwards enters the pond internal upper part gas space.
The power source that impels water vapor in the containment 14 and incoagulability gas constantly to enter constrain pond 13 is the pressure differential between containment 14 and the constrain pond 13.Constrain pond 13 interior original pressures are identical with containment 14, and pressure and containment 14 interior situations and pond body bulk have very large the contact during operation, therefore in the situation that permission should increase constrain pond 13 volumes as far as possible.
Atmosphere after the accident in the containment 14 enters constrain pond 13, constrain pond 13 interior bottom water at low temperature are with the water vapour condensation that enters, can slow down containment 14 internal pressures rises, simultaneously fouling gas is accumulated to the pond internal upper part, reduce gradually containment 14 interior fouling gas concentration, such as nitrogen, oxygen, hydrogen etc., the reduction of fouling gas concentration, both can promote containment 14 cooling systems to carry out the function of steam-condensation heat extraction, can prevent again the generation of hydrogen explosion.
After accident (for example small break LOCA or Main steam line break accident) occurs, under voltage stabilizer 3 low-voltage signals, trigger the shutdown of reactor automatic emergency, and produce engineered safeguards features trigger pip (S signal).The S signal triggers emergence core stacking cool system (Core makeup tank 5, afterheat heat exchanger 9 etc.) and starts.When reactor coolant loop was depressured to certain level, peace was annotated case 6 and is started.When peace notes case 6 water levels drop to certain level, high temperature coolant in the containment 14 is cooled off by containment 14 the second outer heat interchanger 12, not only coolant system is carried out decrease temperature and pressure, also the heat in the containment 14 is directly exported to beyond the containment 14, alleviate the heat load of containment 14.
The S signal triggers simultaneously First Heat Exchanger 11 and starts, and containment 14 interior steam enter and carry out condensing heat-exchange in the First Heat Exchanger 11, and condensate water is injected in the material-changing water tank 8, as the peace water filling source of later stage containment 14 built-in material-changing water tanks 8.
And the valve on 13 inlet pipes of constrain pond is opened all the time, therefore communicates with containment 14 interior spaces, as long as containment 14 internal pressures rise after the accident, system will rely on pressure differential to carry out its security function.In case containment 14 interior temperature are higher than containment 14 outer temperature, the steel containment vessel internal face carries out heat transfer free convection and condensing heat-exchange, steel containment vessel outside wall surface air carries out heat transfer free convection, steel containment vessel carries out the heat conduction, and this process is delivered to the heat in the containment 14 outside the containment 14.
Process after the accident is divided into former and later two time periods: stage, material-changing water tank 8 that material-changing water tank 8 directly injects before the beginning directly inject the later long-term cool cycles stage of beginning.In front the stage, constrain Chi13Shui relies on the heat in First Heat Exchanger 11, the second heat interchanger 12 discharge containments 14 simultaneously as the short term thermal trap, and the active hypotensive effect of the second heat interchanger can impel reactor to enter into as early as possible the long-term cool cycles stage; Simultaneously, constrain pond 13 can reduce fouling gas concentration, improve water vapor concentration, helps First Heat Exchanger 11 to play a greater role.
In the back the stage, because material-changing water tank 8 directly injects and melt pit injects, pressure vessel 1 major part is by water logging, and containment 14 interior vapour concentrations increase, and fouling gas concentration significantly reduces, and the effect of First Heat Exchanger 11 strengthens.In the present embodiment, three non-passive safety shell 14 heat passing aways had not only respectively had characteristics, but also had complemented each other.
Understandable, above-mentioned each technical characterictic can combination in any uses and unrestricted.
The above only is embodiment of the present utility model; be not so limit claim of the present utility model; every equivalent structure or equivalent flow process conversion that utilizes the utility model instructions and accompanying drawing content to do; or directly or indirectly be used in other relevant technical fields, all in like manner be included in the scope of patent protection of the present utility model.
Claims (10)
1. PWR nuclear power plant containment cooling system comprises containment, is provided with pressure vessel, the steam generator that is connected with pressure vessel in described containment, is connected to the voltage stabilizer between described pressure vessel and the steam generator and is arranged on material-changing water tank in the described containment; Described pressure vessel also is provided with the direct safety injection pipeline; It is characterized in that,
Described PWR nuclear power plant containment cooling system comprises the cooling system water tank that is arranged on described containment periphery, is arranged on First Heat Exchanger and the second heat interchanger in the described cooling system water tank;
The first inlet tube of described First Heat Exchanger is connected with space in the described containment, and the first outlet of described First Heat Exchanger is connected with described material-changing water tank;
The second inlet tube of described the second heat interchanger is connected with described voltage stabilizer, and the second outlet of described the second heat interchanger is connected with described pressure vessel.
2. PWR nuclear power plant containment cooling system according to claim 1 is characterized in that, described the first inlet tube is communicated with the upper space of described containment, and connecting tube is provided with by-pass valve control;
Described the first outlet is communicated with the bottom of described material-changing water tank, and connecting tube is provided with by-pass valve control.
3. PWR nuclear power plant containment cooling system according to claim 1 is characterized in that, described the second inlet tube is connected with described voltage stabilizer top, and connecting tube is provided with by-pass valve control;
Described the second outlet is connected with described direct safety injection pipeline, and connecting tube is provided with by-pass valve control.
4. PWR nuclear power plant containment cooling system according to claim 1 is characterized in that, the periphery of described containment also is provided with shielding case, is formed with the air ring corridor between described shielding case and the described containment;
The top of described shielding case is provided with air intake; The top, the outside of described containment is provided with air out; Described air intake and air out are communicated with described air ring corridor.
5. PWR nuclear power plant containment cooling system according to claim 4 is characterized in that, described shielding case is the concrete shield shell; Described containment is steel containment vessel.
6. PWR nuclear power plant containment cooling system according to claim 4, it is characterized in that, in described air ring corridor, be provided with from top to down the air baffle, described air baffle is separated into external rings corridor and inner loop corridor with described air ring corridor, and described air baffle forms the baffling space that is communicated with described external rings corridor and inner loop corridor with the bottom of described air ring corridor.
7. PWR nuclear power plant containment cooling system according to claim 1 is characterized in that, described PWR nuclear power plant containment cooling system also comprises constrain pond; The inlet pipe in described constrain pond is communicated with the upper space of described containment.
8. PWR nuclear power plant containment cooling system according to claim 7 is characterized in that, described constrain pond is arranged on the containment periphery.
9. PWR nuclear power plant containment cooling system according to claim 7 is characterized in that, described constrain pond is airtight constrain pond, and the inlet pipe in described constrain pond is provided with the normally open valve door.
10. each described PWR nuclear power plant containment cooling system is characterized in that according to claim 1-9, and described cooling system water tank and pressure vessel are arranged on the containment pedestal, and the absolute altitude of cooling system water tank is higher than the absolute altitude of described pressure vessel.
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| CN2012204610667U CN202855316U (en) | 2012-09-11 | 2012-09-11 | Containment cooling system for PWR (pressurized water reactor) nuclear power plant |
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| CN2012204610667U CN202855316U (en) | 2012-09-11 | 2012-09-11 | Containment cooling system for PWR (pressurized water reactor) nuclear power plant |
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Cited By (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103413581A (en) * | 2013-07-31 | 2013-11-27 | 中科华核电技术研究院有限公司 | Passive containment cooling system |
| CN104733060A (en) * | 2015-03-25 | 2015-06-24 | 东南大学 | Passive residual heat removal system of marine nuclear power device |
| CN104979022A (en) * | 2014-04-03 | 2015-10-14 | 国核（北京）科学技术研究院有限公司 | Non-active containment heat export system and pressurized water reactor |
| CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
| CN106128536A (en) * | 2016-06-30 | 2016-11-16 | 四川行之知识产权运营服务有限公司 | A kind of system of safety coefficient when can improve nuclear energy power generation |
| CN106409357A (en) * | 2016-11-16 | 2017-02-15 | 中广核研究院有限公司 | Reactor with passive reactor core waste heat emission function |
| CN106448757A (en) * | 2016-11-16 | 2017-02-22 | 中广核研究院有限公司 | Reactor with passive reactor core residual heat removal function |
| WO2017045159A1 (en) * | 2015-09-16 | 2017-03-23 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shielding wall combination structure |
| CN107039091A (en) * | 2017-03-31 | 2017-08-11 | 哈尔滨工程大学 | Three generations's nuclear power station shields factory building water-filling multi-layer box structure |
| CN109273115A (en) * | 2018-10-31 | 2019-01-25 | 中国船舶重工集团公司第七〇九研究所 | A kind of the containment heat derivation device and its heat derives method of nuclear power unit |
| CN110349685A (en) * | 2019-07-08 | 2019-10-18 | 中国船舶重工集团公司第七一九研究所 | Suitable for the passive cooling structure of floating heap containment and its design method |
| CN111599492A (en) * | 2020-05-09 | 2020-08-28 | 哈尔滨工程大学 | Press down pipe and applied this suppression pipe's suppression pond |
| CN111883269A (en) * | 2020-08-12 | 2020-11-03 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113035396A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Double-wheel double-blade composite power air blowing type efficient heat exchanger built in containment |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
| CN114203315A (en) * | 2021-11-30 | 2022-03-18 | 中国核动力研究设计院 | Pressurized water reactor cavity liquid level monitoring system |
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2012
- 2012-09-11 CN CN2012204610667U patent/CN202855316U/en not_active Expired - Lifetime
Cited By (26)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103413581A (en) * | 2013-07-31 | 2013-11-27 | 中科华核电技术研究院有限公司 | Passive containment cooling system |
| CN103413581B (en) * | 2013-07-31 | 2016-03-23 | 中科华核电技术研究院有限公司 | passive containment cooling system |
| CN104979022A (en) * | 2014-04-03 | 2015-10-14 | 国核（北京）科学技术研究院有限公司 | Non-active containment heat export system and pressurized water reactor |
| CN104733060A (en) * | 2015-03-25 | 2015-06-24 | 东南大学 | Passive residual heat removal system of marine nuclear power device |
| WO2017045159A1 (en) * | 2015-09-16 | 2017-03-23 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shielding wall combination structure |
| CN105741888A (en) * | 2016-03-29 | 2016-07-06 | 中国人民解放军92609部队 | Non-kinetic energy containment cooling system for pressurized water reactor |
| CN106128536A (en) * | 2016-06-30 | 2016-11-16 | 四川行之知识产权运营服务有限公司 | A kind of system of safety coefficient when can improve nuclear energy power generation |
| CN106409357A (en) * | 2016-11-16 | 2017-02-15 | 中广核研究院有限公司 | Reactor with passive reactor core waste heat emission function |
| CN106448757A (en) * | 2016-11-16 | 2017-02-22 | 中广核研究院有限公司 | Reactor with passive reactor core residual heat removal function |
| CN106448757B (en) * | 2016-11-16 | 2018-05-15 | 中广核研究院有限公司 | A kind of reactor with the discharge of passive residual heat of nuclear core |
| CN106409357B (en) * | 2016-11-16 | 2018-10-23 | 中广核研究院有限公司 | A kind of reactor with the discharge of passive residual heat of nuclear core |
| CN107039091A (en) * | 2017-03-31 | 2017-08-11 | 哈尔滨工程大学 | Three generations's nuclear power station shields factory building water-filling multi-layer box structure |
| CN109273115A (en) * | 2018-10-31 | 2019-01-25 | 中国船舶重工集团公司第七〇九研究所 | A kind of the containment heat derivation device and its heat derives method of nuclear power unit |
| CN109273115B (en) * | 2018-10-31 | 2023-08-15 | 中国船舶重工集团公司第七一九研究所 | Containment heat-conducting device and heat-conducting method for nuclear power plant |
| CN110349685A (en) * | 2019-07-08 | 2019-10-18 | 中国船舶重工集团公司第七一九研究所 | Suitable for the passive cooling structure of floating heap containment and its design method |
| CN111599492A (en) * | 2020-05-09 | 2020-08-28 | 哈尔滨工程大学 | Press down pipe and applied this suppression pipe's suppression pond |
| CN111599492B (en) * | 2020-05-09 | 2023-05-30 | 哈尔滨工程大学 | Pressure restraining pipe and pressure restraining pond using same |
| CN111883269B (en) * | 2020-08-12 | 2022-04-22 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
| CN111883269A (en) * | 2020-08-12 | 2020-11-03 | 中国核动力研究设计院 | System and method for cooling stagnant passive in molten material reactor of floating nuclear power station |
| CN112071454A (en) * | 2020-09-15 | 2020-12-11 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN113140337A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Passive cooling system and method for multi-medium shared cooling channel and reactor |
| CN113035396A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Double-wheel double-blade composite power air blowing type efficient heat exchanger built in containment |
| CN113035393A (en) * | 2021-03-05 | 2021-06-25 | 哈尔滨工程大学 | Self-driven air extraction type passive containment heat removal system |
| CN113140337B (en) * | 2021-03-05 | 2023-09-15 | 国科中子能(青岛)研究院有限公司 | Passive cooling system, method and reactor for multi-medium shared cooling channel |
| CN114203315A (en) * | 2021-11-30 | 2022-03-18 | 中国核动力研究设计院 | Pressurized water reactor cavity liquid level monitoring system |
| CN114203315B (en) * | 2021-11-30 | 2024-01-30 | 中国核动力研究设计院 | Pressurized water reactor cavity liquid level monitoring system |
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Address after: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13 Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee after: CHINA GENERAL NUCLEAR POWER Corp. Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13 Patentee before: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Co.,Ltd. Patentee before: CHINA GUANGDONG NUCLEAR POWER GROUP Co.,Ltd. |
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Granted publication date: 20130403 |
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