CN111933316B - Method for efficiently cooling reactor cavity area of pressurized water reactor - Google Patents
Method for efficiently cooling reactor cavity area of pressurized water reactor Download PDFInfo
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- CN111933316B CN111933316B CN202010805864.6A CN202010805864A CN111933316B CN 111933316 B CN111933316 B CN 111933316B CN 202010805864 A CN202010805864 A CN 202010805864A CN 111933316 B CN111933316 B CN 111933316B
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- 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
- G21C15/253—Promoting flow of the coolant for gases, e.g. blowers
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- 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
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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 invention discloses a method for efficiently cooling a reactor cavity area of a pressurized water reactor.A cooling air is introduced into an air flow channel through an air inlet, and the bottom of a pressure container heat preservation layer, the upper part of the pressure container heat preservation layer and a top concrete floor area adjacent to the pressure container heat preservation layer, the inner side surface of a pressure container support piece, a bottom concrete floor corresponding to an inner side cooling nozzle, the outer side surface of the pressure container support piece, a bottom concrete floor corresponding to an outer side cooling nozzle, a pressure container heat preservation layer area corresponding to a guide air pipe and a high temperature area at the position of the top concrete floor corresponding to the pressure container heat preservation layer are sequentially cooled. The invention eliminates the air pipes which are required to be arranged in the reactor cavity nozzle area for cold air supply, saves the overhaul space of the pressure vessel area and the reactor cavity nozzle area, reduces the amount of radioactive solid waste which needs to be treated during retirement, reduces the material and construction amount, and reduces the production cost.
Description
Technical Field
The invention relates to the field of cooling of reactor cavity area temperature of nuclear reactors, in particular to a method for efficiently cooling a reactor cavity area of a pressurized water reactor.
Background
Pressure vessel retention (IVR) technology refers to the containment of core melt within a pressure vessel after a severe accident in a nuclear power plant by employing a series of strategies or means to maintain the integrity of the pressure vessel, thereby limiting the consequences of the severe accident within a loop boundary. Such as injecting water into the reactor cavity, immersing the reactor pressure vessel in water, cooling the pressure vessel wall by boiling heat transfer from the water, and removing the melt decay heat. IVR technology has been widely used in already running or in-building nuclear power plants due to its advantages such as simple implementation and good implementation.
In actual engineering, when the temperature of the pressure vessel is increased to the normal operation temperature of the power plant, the average temperature of the reactor cavity area is 300 ℃, and the average temperature exceeds the standard limit value requirement on the concrete temperature (the average temperature should not exceed 65.6 ℃, and the local maximum temperature should not exceed 93.3 ℃), so that the local heat dissipation capacity is larger; in addition, the reactor body in the reactor cavity area, the hot pipelines of the reactor coolant system and the like are compact in structural arrangement, so that the space is narrow, the heat dissipation efficiency is reduced, and meanwhile, the difficulty is also improved for the arrangement of the cooling ventilation pipelines.
In the prior art, the temperature cooling of the reactor cavity area of the pressurized water reactor needs to consider the cooling of three main parts at the same time: 1) A heat insulation layer at the lower part of the pressure vessel and an out-of-stack nuclear measuring instrument; 2) A pressure vessel support; 3) An upper insulation layer of the pressure vessel and a nozzle region of the reactor pressure vessel.
The reactor cavity area cooling modes of different pressurized water reactor nuclear motor types are different:
(1) And M310 and CPR1000 stacks are formed by feeding cooling air to the pressure vessel support member through one air pipe to cool the support member of the pressure vessel, feeding cooling air to the pressure vessel heat preservation layer part of the reactor cavity region through the other air pipe, and converging the cooling air after passing through the pressure vessel support member and the cooling pressure vessel heat preservation layer respectively to cool the nozzle region at the upper part of the reactor cavity region.
(2) In the reactor cavity area of the first AP1000 reactor in China, fig. 1 is a schematic diagram of air cooling in the lower area of the AP1000 reactor cavity, as shown in fig. 1, cooling air is fed into the lower part of the reactor cavity 12 through an air inlet 11, the cooling air moves upwards from the bottom of a pressure container to cool a heat insulation layer 2 of the pressure container, and the cooling air continuously moves upwards through an air flow channel 1 to enter a cooling flow channel in a pressure container support piece 5 and then directly enters the upper part of the reactor cavity 12 area; fig. 2 is a schematic view of air cooling in the upper region of the reactor cavity of the AP1000, and as shown in fig. 2, two ventilation pipes, namely, a first ventilation pipe 17 and a second ventilation pipe 18, are additionally arranged in the nozzle region of the pressure vessel located in the upper region of the reactor cavity 12 for cooling. In order to introduce the air pipe for conveying the cooling air to the nozzle area, the overhaul space of the upper nozzle area of the steam generator and the reactor pressure vessel is occupied; meanwhile, when the reactor runs at full power, the maximum design radiation dosage rate of the reactor cavity area is more than 5.0Gy/h, and the reactor cavity area is a high radiation area, so that the material is arranged in the reactor cavity area to finally form high-radioactivity solid waste.
Disclosure of Invention
The invention aims to solve the technical problems and provide a method for efficiently cooling a reactor cavity area of a pressurized water reactor, which is more economical, has smaller engineering quantity and can reduce radioactive solid waste to be treated in retirement.
The technical scheme adopted by the invention is as follows:
a method for efficiently cooling a reactor cavity area of a pressurized water reactor comprises the steps of using a fan to enable cooling air to be introduced into an air flow channel at the lower part of the reactor cavity area through an air inlet, and cooling the bottom of a pressure vessel heat preservation layer at the lower part of the reactor cavity area; continuously driving the cooling air to move upwards along the air flow channel, so that a part of the cooling air is sprayed upwards through a vertical nozzle arranged on the air flow channel plugging flange to cool the upper part of the pressure vessel insulating layer and the top concrete floor area adjacent to the pressure vessel insulating layer, and the other part of the cooling air enters the guide air cover; cooling air entering the guide fan cover is sprayed out through an inner side cooling nozzle arranged at the bottom of the guide fan cover to cool the inner side surface of the pressure container support piece and the bottom concrete floor slab corresponding to the inner side cooling nozzle, and the other part of cooling air continues upwards along the air flow channel to enter a cooling flow channel arranged in the pressure container support piece; cooling air entering the cooling flow channel, wherein one part of the cooling air is sprayed out through an outer side cooling nozzle at the bottom of the plugging fan cover, the outer side surface of the pressure container support piece and the bottom concrete floor slab corresponding to the outer side cooling nozzle are cooled, the other part of the cooling air rises along the cooling flow channel, and after the pressure container support piece is cooled, the cooling air is finally sprayed out through a guide air pipe, and the pressure container heat-insulating layer area corresponding to the guide air pipe and the high-temperature area corresponding to the pressure container heat-insulating layer area at the top concrete floor slab are cooled; the air flow channel is a space formed between the pressure vessel heat insulation layer and the vertical concrete wall surface of the reactor cavity.
In the prior art, a pressure vessel in a nuclear power plant adopting IVR technology is arranged in a reactor cavity area through a pressure vessel support piece pre-buried in concrete, the reactor cavity area adopts modularized construction, the pressure vessel adopts a metal reflection type heat preservation system, and the metal reflection type heat preservation system is used for isolating heat emitted by the high-temperature outer surface of the pressure vessel so as to keep the temperature of the reactor cavity concrete below a limit value. The metal reflection type heat preservation system of the pressure vessel can provide an air flow path for guiding cooling air to circulate for cooling the reactor cavity area in normal operation, can also provide a water and steam circulation path for implementing IVR technology in serious accidents, and provides guarantee for water cooling of the pressure vessel.
In the actual production process, the circulation mode of cooling air in the reactor cavity area plays an important role in controlling the temperature of the reactor cavity area.
Preferably, the guiding air pipe is arranged at the upper part of the pressure vessel supporting piece, and the guiding air pipe is circular truncated cone-shaped.
Preferably, the vertical nozzle is arranged at a position staggered from the cold/hot pipe section or the direct injection pipe section.
Preferably, the guiding fan cover is arranged at the bottom of the inner side of the pressure vessel supporting piece, the plugging fan cover is arranged at the bottom of the outer side of the pressure vessel supporting piece, the inner side is close to the heat insulation layer of the pressure vessel, and the outer side is far away from the heat insulation layer of the pressure vessel.
Preferably, one end of the guide fan housing is connected with the wall of the adjacent air flow channel, and the other end of the guide fan housing is fixed on the wall of the pressure vessel support piece at the upper end of the inlet of the cooling flow channel adjacent to the guide fan housing through bolts.
Preferably, one end of the plugging fan housing is fixed on the ground of the bottom concrete floor adjacent to the plugging fan housing, and the other end of the plugging fan housing is fixed on the pressure vessel support wall of the upper end of the cooling flow passage inlet adjacent to the plugging fan housing through bolts.
Preferably, external corners of the upper ends of the guide fan cover and the plugging fan cover are provided with round corners.
Preferably, the reactor cavity area is a reactor cavity area adopting a pressure vessel retention technology.
Preferably, the pressure vessel insulation layer is also provided with a cooling water runner for cooling the reactor by water submerging in severe accidents.
Preferably, the pressure vessel insulation layer is metal reflective.
The invention has the beneficial effects that:
(1) Compared with the prior art, the invention omits an air pipe which is required to be arranged for cold air supply in the reactor cavity nozzle area, saves the overhaul space of the pressure vessel area and the reactor cavity nozzle area, reduces radioactive solid waste which needs to be treated during retirement, reduces materials and construction amount, and improves engineering economy.
(2) The cooling air is finally sprayed out through the guide air pipe, and cools the pressure container heat insulation layer area corresponding to the guide air pipe and the high-temperature area corresponding to the top concrete floor slab, so that the flow of the air in the peripheral area is quickened, the convection heat exchange is enhanced, and the cooling efficiency is improved.
(3) According to the invention, the external corners of the upper end parts of the guide fan cover and the plugging fan cover are round corners, so that the resistance of air entering the pressure container support piece from the air flow channel is reduced, the air circulation speed is improved, the air convection heat exchange efficiency is enhanced, and the cooling efficiency is further improved.
Drawings
FIG. 1 is a schematic illustration of air cooling of a lower region of an AP1000 reactor cavity;
FIG. 2 is a schematic illustration of air cooling of an upper region of an AP1000 reactor cavity;
FIG. 3 is a schematic illustration of cooling air circulation at the bottom of a pressure vessel support;
FIG. 4 is a schematic view of a pressure vessel support and a pilot duct;
FIG. 5 is a schematic cross-sectional view of a pilot duct;
FIG. 6 is a schematic view of an air flow path blocking flange;
the air flow channel type air conditioner comprises an air flow channel 1, a pressure vessel heat preservation layer 2, an air flow channel plugging flange 3, a bottom concrete floor slab 4, a pressure vessel supporting piece 5, a cooling flow channel 6, a guiding air pipe 7, an inner side cooling nozzle 8, a top concrete floor slab 9, a guiding fan housing 10, an air inlet 11, a reactor cavity 12, a cooling water flow channel 13, a vertical nozzle 14, a plugging fan housing 15, an outer side cooling nozzle 16, a first ventilation pipeline 17 and a second ventilation pipeline 18.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
Example 1
The reactor cavity area described in the embodiments of the present invention is a reactor cavity area employing a pressure vessel retention technique.
A method for efficiently cooling a pressurized water reactor cavity region comprises the steps of enabling cooling air to be introduced into an air flow channel 1 at the lower part of a reactor cavity region 12 through an air inlet 11 by using a fan, and cooling the bottom of a pressure vessel insulating layer 2 at the lower part of the reactor cavity region 12.
Fig. 3 is a schematic view showing the circulation of cooling air at the bottom of the pressure vessel support, as shown in fig. 3, the cooling air is continuously driven to move upwards along the air flow channel 1, so that a part of the cooling air is sprayed upwards through vertical nozzles 14 arranged on the air flow channel plugging flange 3, the air flow channel plugging flange 3 and the vertical nozzles 14 are positioned in a relationship shown in the schematic view of the air flow channel plugging flange in fig. 6, the upper part of the pressure vessel insulation layer 2 and the area of the top concrete floor 9 adjacent to the pressure vessel insulation layer 2 are cooled, and the other part of the cooling air enters the guiding air cover 10. The vertical nozzle 14 is positioned offset from the cold/hot or direct injection sections. The pressure vessel heat preservation layer 2 is metal reflection type.
Fig. 4 is a schematic view of the pressure vessel support and the guiding duct, as shown in fig. 4, a part of the cooling air entering the guiding hood 10 is sprayed out through the inner cooling nozzle 8 arranged at the bottom of the guiding hood 10 to cool the inner side surface of the pressure vessel support 5 and the bottom concrete floor 4 corresponding to the inner cooling nozzle 8, and the other part continues upwards along the air flow channel 1 and enters the cooling flow channel 6 arranged in the pressure vessel support 5. The guiding fan cover 10 is arranged at the bottom of the inner side of the pressure vessel supporting piece 5, the plugging fan cover 15 is arranged at the bottom of the outer side of the pressure vessel supporting piece 5, the inner side is close to the pressure vessel heat preservation layer 2, and the outer side is far away from the pressure vessel heat preservation layer 2. One end of the guiding fan cover 10 is connected with the wall of the adjacent air flow channel 1, and the other end is fixed on the wall of the pressure container support piece 5 at the upper end of the inlet of the cooling flow channel 6 adjacent to the guiding fan cover through bolts.
And cooling air entering the cooling flow channel 6 is sprayed out through an outer side cooling nozzle 16 at the bottom of the plugging fan housing 15, the outer side surface of the cooling pressure container support 5 and the bottom concrete floor slab 4 corresponding to the outer side cooling nozzle 16 are cooled, the other part of the cooling air rises along the cooling flow channel 6, after cooling the pressure container support 5, the cooling air is finally sprayed out through the guiding air pipe 7, and the high-temperature area at the pressure container heat preservation layer 2 area corresponding to the guiding air pipe 7 and the top concrete floor slab 9 corresponding to the pressure container heat preservation layer area are cooled. Fig. 5 is a schematic cross-sectional view of a guiding air duct, as shown in fig. 5, the guiding air duct 7 is disposed at the upper portion of the pressure vessel supporting member 5, and the guiding air duct 7 is circular with a circular truncated cone shape. The plugging fan housing 15 is fixed on the ground of the bottom concrete floor slab 4 adjacent to the plugging fan housing at one end, and is fixed on the wall of the pressure vessel support 5 adjacent to the plugging fan housing at the upper end of the inlet of the cooling flow passage 6 through bolts at the other end.
The air flow passage 1 is a space formed between the pressure vessel insulating layer 2 and the vertical concrete wall surface of the reactor cavity 12.
To reduce the resistance to air circulation and increase the air flow rate, the external corners of the upper ends of the guide hood 10 and the blocking hood 15 are rounded.
The pressure vessel insulation layer 2 is also provided with a cooling water runner 13 for cooling the reactor by water submerging in severe accidents.
After the cooling air has been discharged through the air flow channel 1, it is finally discharged out of the reactor cavity area through the penetrations of the hot or cold pipes of the pressure vessel.
The foregoing description of the preferred embodiments of the invention is not intended to limit the invention to the particular embodiments disclosed, but on the contrary, the intention is to cover all modifications, equivalents, and alternatives falling within the spirit and scope of the invention as defined by the appended claims.
Claims (6)
1. A method for efficiently cooling a reactor cavity area of a pressurized water reactor is characterized in that: cooling air is led into an air flow channel (1) at the lower part of a reactor cavity area (12) through an air inlet (11) by using a fan, and the bottom of a pressure vessel insulating layer (2) at the lower part of the reactor cavity area (12) is cooled; continuing to drive the cooling air to move upwards along the air flow channel (1), so that part of the cooling air is sprayed upwards through vertical nozzles (14) arranged on the air flow channel plugging flange (3) to cool the upper part of the pressure vessel insulating layer (2) and the area of the top concrete floor (9) adjacent to the pressure vessel insulating layer (2), and the other part of the cooling air enters the guide fan cover (10); cooling air entering the guide fan housing (10) is sprayed out through an inner side cooling nozzle (8) arranged at the bottom of the guide fan housing (10) to cool the inner side surface of the pressure vessel support (5) and the bottom concrete floor (4) corresponding to the inner side cooling nozzle (8), and the other part continues upwards along the air flow channel (1) to enter a cooling flow channel (6) arranged in the pressure vessel support (5); cooling air entering the cooling flow channel (6), wherein one part of the cooling air is sprayed out through an outer side cooling nozzle (16) arranged at the bottom of the plugging fan cover (15), the outer side surface of the cooling pressure container support (5) and the bottom concrete floor (4) corresponding to the outer side cooling nozzle (16) are cooled, the other part of the cooling air rises along the cooling flow channel (6), after cooling the cooling pressure container support (5), the cooling air is finally sprayed out through a guide air pipe (7), and the high-temperature area at the pressure container heat insulation layer (2) area corresponding to the guide air pipe (7) and the top concrete floor (9) corresponding to the pressure container heat insulation layer area is cooled; the air flow channel (1) is a space formed between the pressure vessel heat preservation layer (2) and the vertical concrete wall surface of the reactor cavity (12);
the guide air pipe (7) is arranged at the upper part of the pressure vessel supporting piece (5), and the guide air pipe (7) is circular truncated cone-shaped;
the guide fan cover (10) is arranged at the bottom of the inner side of the pressure vessel supporting piece (5), the plugging fan cover (15) is arranged at the bottom of the outer side of the pressure vessel supporting piece (5), the inner side is close to one side of the pressure vessel heat preservation layer (2), and the outer side is far away from one side of the pressure vessel heat preservation layer (2);
one end of the guide fan cover (10) is connected with the wall of the adjacent air flow channel (1), and the other end of the guide fan cover is fixed on the wall of the pressure vessel support piece (5) at the upper end of the inlet of the cooling flow channel (6) adjacent to the guide fan cover through bolts;
one end of the plugging fan cover (15) is fixed on the ground of the bottom concrete floor slab (4) adjacent to the plugging fan cover, and the other end of the plugging fan cover is fixed on the wall of the pressure vessel support piece (5) adjacent to the upper end of the inlet of the cooling flow passage (6) through bolts.
2. A method of efficiently cooling a pressurized water reactor cavity region according to claim 1, wherein: the vertical nozzle (14) is arranged at a position staggered with the cold/hot pipe section or the direct injection pipe section.
3. A method of efficiently cooling a pressurized water reactor cavity region according to claim 1, wherein: external corners of the upper end parts of the guide fan cover (10) and the blocking fan cover (15) are round corners.
4. A method of efficiently cooling a pressurized water reactor cavity region according to claim 1, wherein: the reactor cavity area is a reactor cavity area adopting a pressure vessel retention technology.
5. A method of efficiently cooling a pressurized water reactor cavity region according to claim 1, wherein: and a cooling water runner (13) for cooling the reactor by water submerging under serious accidents is also arranged on the pressure vessel heat preservation layer (2).
6. A method of efficiently cooling a pressurized water reactor cavity region according to claim 1, wherein: the pressure vessel heat preservation layer (2) is metal reflection type.
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Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE4032032A1 (en) * | 1989-10-24 | 1991-04-25 | Siemens Ag | Emergency coolant supply - for PWR through elbow directing flow of coolant in downcomer |
| JP2011021901A (en) * | 2009-07-13 | 2011-02-03 | Toshiba Corp | Passive cooling system for liquid metal cooled reactor |
| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
| CN105280249A (en) * | 2015-09-16 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shield walling composite structure |
| CN106062883A (en) * | 2014-01-31 | 2016-10-26 | 俄罗斯联邦诺萨顿国家原子能公司 | Reactor system with a lead-cooled fast reactor |
| 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 |
| WO2017127937A1 (en) * | 2016-01-29 | 2017-08-03 | Terrestrial Energy Inc. | Cooling system for nuclear reactor |
| CN109147969A (en) * | 2018-09-13 | 2019-01-04 | 中国核动力研究设计院 | Nuclear reactor fusant reactor core is detained passive cooling system |
| CN209729521U (en) * | 2019-03-28 | 2019-12-03 | 中国核电工程有限公司 | A kind of heat discharge system applied to large nuclear-power factory reactor pit region |
| CN209804277U (en) * | 2019-03-15 | 2019-12-17 | 中国核电工程有限公司 | Ventilation system and pressurized water reactor nuclear power plant reactor top system |
Family Cites Families (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8401142B2 (en) * | 2007-02-20 | 2013-03-19 | Westinghouse Electric Company Llc | Nuclear reactor vessel fuel thermal insulating barrier |
| JP2009198400A (en) * | 2008-02-22 | 2009-09-03 | Mitsubishi Heavy Ind Ltd | Cooling structure and method of control rod drive unit and nuclear reactor |
| KR101653942B1 (en) * | 2016-02-23 | 2016-09-02 | 문인득 | Cooling apparatus for the structure under steam generator of atomic reactor |
| CN206572970U (en) * | 2017-03-21 | 2017-10-20 | 山东墨龙石油机械股份有限公司 | Water cooling plugging device |
| CN107293339A (en) * | 2017-06-09 | 2017-10-24 | 中广核工程有限公司 | Nuclear power plant's Passive containment cooling system |
| CN208570123U (en) * | 2018-07-20 | 2019-03-01 | 中广核研究院有限公司 | A kind of small-sized heap primary Ioops main equipment structure of novel compact Layout |
| KR102295616B1 (en) * | 2018-12-28 | 2021-08-31 | 한국전력기술 주식회사 | Concrete air cooling system using the embedded pipe |
| CN110111914A (en) * | 2019-04-28 | 2019-08-09 | 中广核研究院有限公司 | A kind of nuclear reactor and its in-pile component |
-
2020
- 2020-08-12 CN CN202010805864.6A patent/CN111933316B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE4032032A1 (en) * | 1989-10-24 | 1991-04-25 | Siemens Ag | Emergency coolant supply - for PWR through elbow directing flow of coolant in downcomer |
| JP2011021901A (en) * | 2009-07-13 | 2011-02-03 | Toshiba Corp | Passive cooling system for liquid metal cooled reactor |
| CN106062883A (en) * | 2014-01-31 | 2016-10-26 | 俄罗斯联邦诺萨顿国家原子能公司 | Reactor system with a lead-cooled fast reactor |
| CN104269194A (en) * | 2014-10-13 | 2015-01-07 | 中国科学院合肥物质科学研究院 | Temperature-triggered passive accident residual heat removal system for pool type reactor |
| CN105280249A (en) * | 2015-09-16 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant reactor pressure vessel and shield walling composite structure |
| 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 |
| WO2017127937A1 (en) * | 2016-01-29 | 2017-08-03 | Terrestrial Energy Inc. | Cooling system for nuclear reactor |
| CN109147969A (en) * | 2018-09-13 | 2019-01-04 | 中国核动力研究设计院 | Nuclear reactor fusant reactor core is detained passive cooling system |
| CN209804277U (en) * | 2019-03-15 | 2019-12-17 | 中国核电工程有限公司 | Ventilation system and pressurized water reactor nuclear power plant reactor top system |
| CN209729521U (en) * | 2019-03-28 | 2019-12-03 | 中国核电工程有限公司 | A kind of heat discharge system applied to large nuclear-power factory reactor pit region |
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