CN105280249A - Nuclear power plant reactor pressure vessel and shield walling composite structure - Google Patents
Nuclear power plant reactor pressure vessel and shield walling composite structure Download PDFInfo
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- CN105280249A CN105280249A CN201510586928.7A CN201510586928A CN105280249A CN 105280249 A CN105280249 A CN 105280249A CN 201510586928 A CN201510586928 A CN 201510586928A CN 105280249 A CN105280249 A CN 105280249A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- 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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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
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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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- 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 present invention provides a nuclear power plant reactor pressure vessel and shielding wall composite structure comprising a reactor pit shielding wall, a reactor pit enclosed by the reactor pit shielding wall, a reactor pressure vessel arranged in the reactor pit, and a thermal insulation layer arranged outside the reactor pressure vessel, up-and-down-through flow channels are respectively arranged between the thermal insulation layer and the reactor pressure vessel, and the thermal insulation layer and the reactor pit shielding wall, the lower part of the reactor pit shielding wall is provided with a reactor pit water injection pipeline in the manner of penetration, an accommodation space is arranged on the inner wall of the upper part of the reactor pit shielding wall, a return flow path is arranged in the reactor pit shielding wall, and the return flow path is used for communicating the accommodation space and the reactor pit bottom space. Compared with the prior art, the return flow path is arranged in the reactor pit shielding wall to ensure saturated water entrained by steam can smoothly flow back into the reactor pit, so that a stable natural circulation can be formed between a rising flow path and the return flow path in the reactor pit to ensure the reactor pressure vessel can be continuedly and rapidly cooled under severe accident conditions.
Description
Technical field
The invention belongs to nuclear plant severe accident reply field, more particularly, the present invention relates to and a kind ofly can tackle the nuclear power plant reactor pressure vessel of major accident operating mode and the unitized construction of barrier shield.
Background technology
After Chernobyl, three miles of islands, Fukushima nuclear power plant accident, the attention of countries in the world to Nuclear Safety reaches unprecedented height, while requirements at the higher level are proposed to nuclear power station generation major accident probability of future generation, one after another in-service in conjunction with various countries, in the nuclear power generating sets feature of building, severe accident relieving stragetic innovation scheme is proposed.In the new edition " nuclear power plant design safety regulation " (HAF102) and IAEA directive/guide NS-G-1.10 of the issue on April 18th, 2014 of Chinese nuclear safety office, also require that nuclear power station is considered to arrange major accident prevention and mitigation strategy with should using up actual capabilities in the design.
After pressurized-water reactor nuclear power plant generation major accident, if cooling way lost efficacy in heap, reactor core will melt gradually and caves in and fall into bottom reactor pressure vessel.Now, if can not get effective external refrigeration, reactor pressure vessel will be fused, cause piling interior fused mass and be detained inefficacy, reactor core fused mass enters into reactor pit, then there is MCCI with concrete floor and react (fused mass and concrete react) and the inflammable gas discharging harmfulness, thus major accident situation is significantly worsened.
Inefficacy is detained for preventing piling interior fused mass, part openly pressurized-water reactor nuclear power plant adopts out-pile type of cooling cooled reactor pressure vessel, that is: under major accident operating mode to water filling in reactor pit, reactor pressure vessel is made to be immersed in reactor pit water body, guarantee that reactor pressure vessel is not fused by the outer wall type of cooling, thus make to pile interior fused mass and can be stably trapped in reactor pressure vessel.For preventing the reactor pressure vessel burn through phenomenon because critical heat flux density deficiency causes, heat eliminating medium must with larger traffic flow through reactor pressure vessel outer wall, therefore, need for reactor pressure vessel external refrigeration medium provides suitable runner design, manage to make heap cooling medium outside produce stronger Natural Circulation effect.Usually, suitable gap can be set between reactor pressure vessel outer wall and its heat-insulation layer, and set out steam ports and water inlet respectively in heat-insulation layer top and the bottom, under major accident operating mode, top venthole and lower water inlet rely on non-active principle automatically to open, thus provide rising runner for out-pile cools.Due in the steam water interface that venthole place, top discharges, quality of steam share very little (about 1% magnitude), principal ingredient is saturation water, only manages to make this part saturation water be back to bottom reactor pit with less pressure drop, could form strongly stable out-pile cooling Natural Circulation effect.Experiment and analytical proof, the natural circulation flow strengthening out-pile cooling is conducive to improving critical heat flux density, thus can ensure out-pile cooling power better.
In the published nuclear power design of part, be designed to out-pile cooling by the special construction of reactor pressure vessel support ring and Natural Circulation backflow runner is provided, but part nuclear power plant reactor support ring is because of demands such as seismic design, its upper surface, higher than reactor pit overflow absolute altitude, cannot provide backflow runner by it for out-pile cools.For this reason, need adjustment reactor pit structural design scheme, solve the backflow runner problem of its out-pile cooling.In addition, reactor pit compact conformation, its functional requirement is more, needs reasonable integration normally to run and Functional Design under major accident, and under this framework, solve the backflow runner problem of out-pile cooling.
Summary of the invention
The object of the invention is to: the unitized construction that a kind of nuclear power plant reactor pressure vessel and barrier shield are provided, to ensure that heat eliminating medium can form stable Natural Circulation under major accident operating mode, more effectively reactor pressure vessel is cooled, guarantee the integrality of reactor pressure vessel.
To achieve these goals, the invention provides the unitized construction of a kind of nuclear power plant reactor pressure vessel and barrier shield, it comprises reactor pit barrier shield, the reactor pit surrounded by reactor pit barrier shield, the heat-insulation layer that is arranged on the reactor pressure vessel in reactor pit and is arranged on outside reactor pressure vessel, between heat-insulation layer and reactor pressure vessel, all there is the runner of up/down perforation between heat-insulation layer and reactor pit barrier shield; The bottom of reactor pit barrier shield is equipped with reactor pit waterflood-transmission line; The upper inside wall of described reactor pit barrier shield offers takes space in, is provided with the backflow runner that will take space in and be communicated with reactor pit bottom space in reactor pit barrier shield.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and described backflow runner comprises the outlet at bottom for being communicated with reactor pit bottom space, and outlet at bottom place is provided with openable block piece; Under nominal situation, the outlet at bottom of backflow runner is closed by block piece, avoids reactor pit normally to blow from the bypass of backflow runner; Under major accident operating mode, block piece relies on non-active principle automatically to open, and makes backflow runner unimpeded, guarantees that the heap cooling medium outside of taking in space is back to bottom reactor pit smoothly.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the runner between described heat-insulation layer and reactor pressure vessel is the rising runner piling cooling medium outside under major accident; Under major accident operating mode, described rising runner and backflow runner form natural convection loop under the effect of Media density difference, continue to carry out external refrigeration to reactor pressure vessel.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the space that takes in of described reactor pit barrier shield is imported and exported by main pipeline and is communicated with reactor pit space outerpace; Under major accident operating mode, vapour-liquid blending agent in rising runner is separated into steam and saturation water taking in space, wherein steam is imported and exported by the main pipeline on reactor pit barrier shield and is discharged reactor pit and take away reactor pit heat, and isolated saturation water is flow back into bottom reactor pit again by backflow runner.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the bottom of described heat-insulation layer offers water injection hole, leaves venthole between top and reactor pressure vessel; Top venthole and the bottom water injection hole of heat-insulation layer are closed at ordinary times, rely on non-active principle automatically to open under major accident operating mode, thus form the rising runner of heap cooling medium outside between reactor pressure vessel and heat-insulation layer.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and described water injection hole is all positioned at below the low head of reactor pressure vessel.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the top entry of described backflow runner is positioned at the minimum point that reactor pit barrier shield takes space in.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and taking in of described reactor pit barrier shield is spatially located at main pipeline of reactor nozzle belt absolute altitude place, and is annular.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the top of described reactor pressure vessel is connected with many main pipelines, and main pipeline correspondingly main conduit is imported and exported and passed reactor pit barrier shield; The size that main pipeline is imported and exported is greater than the cross-sectional area of main pipeline, thus will take space in and be communicated with reactor pit space outerpace.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, the diapire that described annular takes space in is provided with support ring, support ring is formed the root of all main pipelines and supports, such that reactor pressure vessel is unsettled to be housed in reactor pit; The top entry of backflow runner is positioned at taking on the diapire of space outside support ring.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the diapire that described main pipeline is imported and exported takes the diapire in space in higher than annular, and the top entry of backflow runner is positioned at the minimum point that annular takes space diapire in.
One as the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield is improved, and the runner between described heat-insulation layer and reactor pit barrier shield is normal vent flow path, is used as the gas channel that reactor pit ventilates in normal conditions.
Compared with prior art, the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield by arranging backflow runner in reactor pit barrier shield, ensure that the saturation water of entrainment with steam can flow back to reactor pit smoothly, therefore, it is possible to rising runner in reactor pit and formed between backflow runner and stablize Natural Circulation, guarantee that reactor pressure vessel cools under major accident operating mode with obtaining Fast Persistence, thus effectively fused mass is trapped in reactor pressure vessel.
Accompanying drawing explanation
Below in conjunction with the drawings and specific embodiments, the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield and Advantageous Effects thereof are described in detail, wherein:
Fig. 1 is the schematic diagram of the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield.
Embodiment
In order to make, object of the present invention, technical scheme and Advantageous Effects are more clear to be understood, below in conjunction with the drawings and specific embodiments, is further elaborated to the present invention.Should be understood that, the embodiment described in this instructions is only used to explain the present invention, is not to limit the present invention.
Refer to Fig. 1, the reactor pressure vessel 30 that the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield comprises reactor pit barrier shield 10, the reactor pit 20 surrounded by reactor pit barrier shield 10 and is arranged in reactor pit 20.Reactor pressure vessel 30 is connected with the many main pipelines 32 passed from reactor pit barrier shield 10 on top.
Reactor pit barrier shield 10 comprises side wall 12 and base plate 14.Side wall 12 has an annular space 120 that takes in and imports and exports 122 with multiple by taking the main pipeline that space 120 is communicated with reactor pit space outerpace on the inwall on top; Take the absolute altitude place that space 120 is positioned at main pipeline of reactor nozzle belt in.It is corresponding with the quantity of main pipeline 32 and position that main pipeline imports and exports quantity and the position of 122.The diapire taking space 120 in is provided with support ring 16, and support ring 16 is formed the root of all main pipelines 32 and supports, such that reactor pressure vessel 30 is unsettled to be housed in reactor pit 20.The size importing and exporting 122 due to main pipeline is greater than the cross-sectional area of main pipeline 32, and does not adopt sealing to arrange therebetween, and therefore main pipeline imports and exports 122 becomes reactor pit 20 and take the passage that space 120 is communicated with space outerpace in.Main pipeline imports and exports the diapire of 122 higher than the diapire taking space 120 in, and main pipeline import and export 122 form the venthole of reactor pit barrier shield 10 jointly with taking space 120 in.The lower seal of side wall 12 is equipped with reactor pit waterflood-transmission line 18, and the outlet of reactor pit waterflood-transmission line 18 is positioned at the position bottom reactor pit 20, under major accident operating mode to water filling in reactor pit 20.Reactor pit waterflood-transmission line 18 is connected with water sources such as material-changing water tanks in reactor pit water supply tank, containment, by non-active, active or the two mode combined to water filling in reactor pit 20.
In order to ensure the efficiency of reactor pressure vessel 30 external refrigeration, also there is heat-insulation layer 34 in its outer setting.Heat-insulation layer 34 is connected with the inwall of reactor pit barrier shield 10 by external support (not shown), its inwall and reactor pressure vessel 30 are without being connected, therefore, there is the gap of up/down perforation between the inwall of heat-insulation layer 34 and the outer wall of reactor pressure vessel 30.And the bottom of heat-insulation layer 34 offers water injection hole 340, water injection hole 340 is horizontally arranged in below the low head of reactor pressure vessel 30, and venthole also and between reactor pressure vessel 30 is left in the top of heat-insulation layer 34.The top venthole of heat-insulation layer 34 and bottom water injection hole 340 flat time close, under major accident operating mode, then rely on non-active principle automatically to open, thus between reactor pressure vessel 30 and heat-insulation layer 34, form rising runner A, for piling the rising of cooling medium outside under major accident operating mode.The outer wall of heat-insulation layer 34 is not fitted with the inwall of reactor pit barrier shield 10 yet, therefore between reactor pit barrier shield 10 and heat-insulation layer 34, also there is the gap of up/down perforation, this gap is connected with reactor pit aeration structure (not shown), for the reactor pit draft passage of nuclear power station reactor core normal operation period, be called normal vent flow path B.
In order to enable chilled water form Natural Circulation in reactor pit 20, the present invention is also provided with the backflow runner 124 for out-pile cooling under major accident in the side wall 12 of reactor pit barrier shield 10.The top entry of backflow runner 124 is located at and is taken on the diapire of space 120 outside support ring 16, and whole passage is through the major part height of side wall 12, and outlet at bottom is located on the position of side wall 12 inner wall lower bottom reactor pit 20.Smooth and easy in order to ensure backflow, the top entry position of backflow runner 124 is the minimum points of taking space 120 diapire in.The outlet at bottom place of backflow runner 124 is provided with reverse checkvalve or other have the block piece opened 126 of similar functions.In normal conditions, block piece 126 closes, and reactor pit air-supply can not from the bypass of backflow runner 124, and backflow runner 124 does not affect the normal operation function of reactor pit 20 yet; Under major accident operating mode, block piece 126 relies on non-active principle automatically to open, and backflow runner 124 is opened unimpeded, for saturation water provides return flow path, thus forms with rising runner A the Natural Circulation runner that out-pile cools.
The job step of nuclear power station of the present invention under major accident operating mode is used to be:
1) when reactor pressure vessel 30 outlet temperature reaches 650 DEG C, in reactor pit 20, chilled water is injected by reactor pit waterflood-transmission line 18, water flooding regime is: starting stage large discharge water filling, to be full of reactor pit 20 fast, floods the bottom outer wall of reactor pressure vessel 30; Follow-up with low discharge water filling, to supplement the water yield of evaporating because of cooled reactor pressure vessel;
2) the bottom water injection hole 340 of heat-insulation layer 34 and top venthole and the block piece 126 of being located at backflow runner 124 outlet at bottom place are opened all automatically; The chilled water entered in reactor pit 20 is divided into two-way: lead up to water injection hole 340, cools via the wall of rising runner A to pressure vessel 30; One tunnel enters and stays in normal vent flow path B, cools reactor pit 20 entirety;
3) entering the cooling water flow in rising runner A when the low head section of reactor pressure vessel 30 is heated to nucleateboiling, form vapour-liquid blending agent, after this blending agent rises to the top of rising runner A, flow out via the space between reactor pressure vessel 30 and heat-insulation layer 34, support ring 16, enter and take space 120 in;
4) vapour-liquid blending agent is taken in space 120 in annular and is separated into steam and saturation water, and wherein steam is imported and exported 122 discharge reactor pits by the main pipeline on reactor pit barrier shield 10 and taken away reactor pit heat; Isolated saturation water flow back into the bottom of reactor pit 20 by backflow runner 124;
5) now, namely rising runner A and backflow runner 124 constitute the natural convection loop of out-pile cooling: the heap cooling medium outside in rising runner A is liquid-vapor mixture, and its density is less; Heap cooling medium outside in backflow runner 124 is saturation water, and its density is larger; The density difference of rising runner A and backflow runner 124 defines larger Natural Circulation driving force, makes the cooling fluid flowing through reactor pressure vessel 30 outer wall have high flow velocities, thus continues to cool reactor pressure vessel 30 efficiently.
Known by describing above, the unitized construction of nuclear power plant reactor pressure vessel of the present invention and barrier shield by offering the runner 124 that refluxes in the side wall 12 of reactor pit barrier shield 10, achieve and utilize the formation in rising runner A and backflow runner 124 of heap cooling medium outside density difference to stablize Natural Circulation, therefore under major accident operating mode, can cool with carrying out Fast Persistence reactor pressure vessel 30, thus effectively fused mass is trapped in reactor pressure vessel 30, keep the integrality of reactor pressure vessel 30.
According to above-mentioned principle, the present invention can also carry out suitable change and amendment to above-mentioned embodiment.Therefore, the present invention is not limited to embodiment disclosed and described above, also should fall in the protection domain of claim of the present invention modifications and changes more of the present invention.In addition, although employ some specific terms in this instructions, these terms just for convenience of description, do not form any restriction to the present invention.
Claims (12)
1. the unitized construction of a nuclear power plant reactor pressure vessel and barrier shield, comprise reactor pit barrier shield, the reactor pit surrounded by reactor pit barrier shield, the heat-insulation layer that is arranged on the reactor pressure vessel in reactor pit and is arranged on outside reactor pressure vessel, between heat-insulation layer and reactor pressure vessel, between heat-insulation layer and reactor pit barrier shield, all there is the runner of up/down perforation; The bottom of reactor pit barrier shield is equipped with reactor pit waterflood-transmission line; It is characterized in that: the upper inside wall of described reactor pit barrier shield offers takes space in, in reactor pit barrier shield, be provided with the backflow runner that will take space in and be communicated with reactor pit bottom space.
2. the unitized construction of nuclear power plant reactor pressure vessel according to claim 1 and barrier shield, is characterized in that: described backflow runner comprises the outlet at bottom for being communicated with reactor pit bottom space, and outlet at bottom place is provided with openable block piece; Under nominal situation, the outlet at bottom of backflow runner is closed by block piece, avoids reactor pit normally to blow from the bypass of backflow runner; Under major accident operating mode, block piece relies on non-active principle automatically to open, and makes backflow runner unimpeded, guarantees that the heap cooling medium outside of taking in space is back to bottom reactor pit smoothly.
3. the unitized construction of nuclear power plant reactor pressure vessel according to claim 1 and 2 and barrier shield, is characterized in that: the runner between described heat-insulation layer and reactor pressure vessel is the rising runner piling cooling medium outside under major accident; Under major accident operating mode, described rising runner and backflow runner form natural convection loop under the effect of Media density difference, continue to carry out external refrigeration to reactor pressure vessel.
4. the unitized construction of nuclear power plant reactor pressure vessel according to claim 3 and barrier shield, is characterized in that: the space that takes in of described reactor pit barrier shield is communicated with reactor pit space outerpace by main pipeline import and export; Under major accident operating mode, vapour-liquid blending agent in rising runner is separated into steam and saturation water taking in space, wherein steam is imported and exported by the main pipeline on reactor pit barrier shield and is discharged reactor pit and take away reactor pit heat, and isolated saturation water is flow back into bottom reactor pit again by backflow runner.
5. the unitized construction of nuclear power plant reactor pressure vessel according to claim 3 and barrier shield, is characterized in that: the bottom of described heat-insulation layer offers water injection hole, leaves venthole between top and reactor pressure vessel; Top venthole and the bottom water injection hole of heat-insulation layer are closed at ordinary times, rely on non-active principle automatically to open under major accident operating mode, thus form the rising runner of heap cooling medium outside between reactor pressure vessel and heat-insulation layer.
6. the unitized construction of nuclear power plant reactor pressure vessel according to claim 5 and barrier shield, is characterized in that: described water injection hole is all positioned at below the low head of reactor pressure vessel.
7. the unitized construction of nuclear power plant reactor pressure vessel according to claim 1 and barrier shield, is characterized in that: the top entry of described backflow runner is positioned at the minimum point that reactor pit barrier shield takes space in.
8. the unitized construction of nuclear power plant reactor pressure vessel according to claim 1 and barrier shield, is characterized in that: taking in of described reactor pit barrier shield is spatially located at main pipeline of reactor nozzle belt absolute altitude place, and is annular.
9. the unitized construction of nuclear power plant reactor pressure vessel according to claim 8 and barrier shield, is characterized in that: the top of described reactor pressure vessel is connected with many main pipelines, and main pipeline main conduit's import and export correspondingly pass reactor pit barrier shield; The size that main pipeline is imported and exported is greater than the cross-sectional area of main pipeline, thus will take space in and be communicated with reactor pit space outerpace.
10. the unitized construction of nuclear power plant reactor pressure vessel according to claim 9 and barrier shield, it is characterized in that: the diapire that described annular takes space in is provided with support ring, support ring is formed the root of all main pipelines and supports, such that reactor pressure vessel is unsettled to be housed in reactor pit; The top entry of backflow runner is positioned at taking on the diapire of space outside support ring.
The unitized construction of 11. nuclear power plant reactor pressure vessels according to claim 9 and barrier shield, it is characterized in that: the diapire that described main pipeline is imported and exported takes the diapire in space in higher than annular, the top entry of backflow runner is positioned at the minimum point that annular takes space diapire in.
The unitized construction of 12. nuclear power plant reactor pressure vessels according to claim 1 and barrier shield, is characterized in that: the runner between described heat-insulation layer and reactor pit barrier shield is normal vent flow path, is used as the gas channel that reactor pit ventilates in normal conditions.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510586928.7A CN105280249B (en) | 2015-09-16 | 2015-09-16 | The combining structure of nuclear power plant reactor pressure vessel and barrier shield |
| GB1521982.7A GB2542442B (en) | 2015-09-16 | 2015-12-14 | Composite construction of nuclear reactor pressure vessel and barrier shield |
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| CN201510586928.7A CN105280249B (en) | 2015-09-16 | 2015-09-16 | The combining structure of nuclear power plant reactor pressure vessel and barrier shield |
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| CN105280249B CN105280249B (en) | 2018-04-27 |
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| CN107039094A (en) * | 2017-05-24 | 2017-08-11 | 长江勘测规划设计研究有限责任公司 | Pressure vessel changeable type underground nuclear power station heap chamber |
| CN107845434A (en) * | 2017-10-27 | 2018-03-27 | 中国核电工程有限公司 | A kind of passive reactor core auxiliary coolant system |
| CN108010591A (en) * | 2017-12-18 | 2018-05-08 | 中广核研究院有限公司 | A kind of multifunctional pressure container reactor pit structure and reactor safety shell structure |
| CN111081395A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Nuclear reactor heat insulation device capable of realizing heat radiation and heat dissipation |
| CN111199806A (en) * | 2019-12-31 | 2020-05-26 | 中国核动力研究设计院 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
| CN111933316A (en) * | 2020-08-12 | 2020-11-13 | 三门核电有限公司 | Method for efficiently cooling reactor cavity area of pressurized water reactor |
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| WO2021138806A1 (en) * | 2020-01-07 | 2021-07-15 | 中广核研究院有限公司 | Safety system for handling severe accident of nuclear power plant and control method therefor |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
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| CN107039094A (en) * | 2017-05-24 | 2017-08-11 | 长江勘测规划设计研究有限责任公司 | Pressure vessel changeable type underground nuclear power station heap chamber |
| CN107039094B (en) * | 2017-05-24 | 2019-02-01 | 长江勘测规划设计研究有限责任公司 | Pressure vessel changeable type underground nuclear power station heap chamber |
| CN107845434A (en) * | 2017-10-27 | 2018-03-27 | 中国核电工程有限公司 | A kind of passive reactor core auxiliary coolant system |
| CN108010591A (en) * | 2017-12-18 | 2018-05-08 | 中广核研究院有限公司 | A kind of multifunctional pressure container reactor pit structure and reactor safety shell structure |
| CN108010591B (en) * | 2017-12-18 | 2024-01-19 | 中广核研究院有限公司 | Multifunctional pressure vessel pit stacking structure and reactor containment structure |
| CN111199806B (en) * | 2019-12-31 | 2022-04-19 | 中国核动力研究设计院 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
| CN111199806A (en) * | 2019-12-31 | 2020-05-26 | 中国核动力研究设计院 | Heat pipe reactor supporting and shielding structure with emergency cooling function |
| CN111081395A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Nuclear reactor heat insulation device capable of realizing heat radiation and heat dissipation |
| WO2021138806A1 (en) * | 2020-01-07 | 2021-07-15 | 中广核研究院有限公司 | Safety system for handling severe accident of nuclear power plant and control method therefor |
| CN113661547A (en) * | 2020-01-07 | 2021-11-16 | 中广核研究院有限公司 | Coping safety system for severe accident of nuclear power plant and control method thereof |
| GB2606803A (en) * | 2020-01-07 | 2022-11-23 | China Nuclear Power Technology Res Inst Co Ltd | Safety system for handling severe accident of nuclear power plant and control method therefor |
| CN111933316A (en) * | 2020-08-12 | 2020-11-13 | 三门核电有限公司 | Method for efficiently cooling reactor cavity area of pressurized water reactor |
| CN111933316B (en) * | 2020-08-12 | 2023-06-02 | 三门核电有限公司 | Method for efficiently cooling reactor cavity area of pressurized water reactor |
| CN112489824A (en) * | 2020-11-26 | 2021-03-12 | 中广核研究院有限公司 | Reactor cabin shielding device for compactly arranging small reactors |
| CN113593733A (en) * | 2021-07-02 | 2021-11-02 | 中国核电工程有限公司 | Passive steel containment heat exporting system |
| CN114155983A (en) * | 2021-10-29 | 2022-03-08 | 中国核电工程有限公司 | Reactor model, reactor ventilation testing device and reactor ventilation testing method |
Also Published As
| Publication number | Publication date |
|---|---|
| GB2542442A (en) | 2017-03-22 |
| CN105280249B (en) | 2018-04-27 |
| GB2542442B (en) | 2019-07-10 |
| GB201521982D0 (en) | 2016-01-27 |
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