CN202771811U - Serious accident processing system capable of charging helium and pressurizing for nuclear power station - Google Patents
Serious accident processing system capable of charging helium and pressurizing for nuclear power station Download PDFInfo
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- CN202771811U CN202771811U CN2012204288550U CN201220428855U CN202771811U CN 202771811 U CN202771811 U CN 202771811U CN 2012204288550 U CN2012204288550 U CN 2012204288550U CN 201220428855 U CN201220428855 U CN 201220428855U CN 202771811 U CN202771811 U CN 202771811U
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- helium
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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 discloses a serious accident processing system capable of charging helium and pressurizing for a nuclear power station and belongs to the field of nuclear power station safety and the technical field of environment protection. The processing system comprises a helium charging and pressurizing conveying system and a safety casing wall face cooling system. The helium charging and pressurizing conveying system comprises a helium supplying source, a pressurizing device and a heating temperature. The helium supplying source is connected with the pressurizing device through a helium conveying pipeline, the pressurizing device is connected with the heating device through double gas conveying pipelines, the double gas conveying pipelines penetrate through a safety casing, the helium supplying source and the pressurizing device are arranged outside the safety casing, the heating device is arranged in the safety casing, and a spraying pipeline is arranged on the heating device. The safety casing wall face cooling system comprises a spraying water tank, a spraying driving structure, an upper spraying head and a lower spraying head. The serious accident processing system has the advantages of active and passive dual systems, fits a single-fault standard, and is high in deposition efficiency of fine particles.
Description
Technical field
The utility model belongs to nuclear plant safety field and environmental protection technical field, relates in particular to a kind of nuclear power station and fills helium pressurization major accident disposal system.
Background technology
The for the third time nuclear plant severe accident of USSR (Union of Soviet Socialist Republics) Chernobyl, U.S.'s Three Mile Island continued on the Fukushima, Japan generation human history in 2011.The radioactive grain thing that accident produces flies away with the wind, along with air motion is transferred, brings immeasurable harm to earth environment and public health.Under the major accident of nuclear power station, may produce a large amount of radioactive grains, effectively remove the life security that these radioactive grains are directly connected to surrounding enviroment and people.Along with the development of science and technology, existing nuclear power station technology is also more and more advanced.Yet, no matter be now moving two generation reactor or the three generations's reactor that is designing, occuring all will to produce the radioactivity fine grained under the major accident.Even advanced the 4th generation supercritical water reactor, also exist specific question: the 4th generation the graphite dust that produces of modular pebble bed high temperature reactor may affect the safety and normal operation of reactor; In the Generation IV sodium-cooled fast reactor, also entail dangers to security of system and people's safety on every side of the migration of sodium particle under the accident conditions.So, in the situation of nuclear power generation major accident, remove for prevention and to delay major accident all be very important to fine grain.
The fine grained that nuclear power station produces mainly is PM
10, PM
2.5Deng fine particle, because its quality is little, specific surface area is large, and is fabulous to the followability of air-flow, be not easy deposition.Conventional dust collection method is all lower to these fine grain removal efficiencies, can't satisfy Nuclear Safety rules and environmental requirement.Mainly adopt at present French sand drift formula filtrator, Sweden's pebble type filtrator and German venturi tubular type filtrator in the design of nuclear power station, mainly for be larger fragment or the coarse particle of reactor that accident produces, unspecial in the Fine Particles under the major accident.Adds in the nuclear power station in two generations and two generations and also to remove fine grained by spray, but the major function of spray system is cooling that the effect that removes particle is relatively poor.Cancelled spray system at three generations AP1000 presurized water reactor, adopt steel containment vessel that water tank is set during major accident and carry out decrease temperature and pressure, the design of water tank is also played the effect that removes particle simultaneously, but this is not the elementary object of waterbox design, and the particulate removal weak effect of water tank.At present for the removing of fine particle under the nuclear plant severe accident, also be in the Primary Study stage.Therefore, in order to guarantee the safety of nuclear power, must searching efficiently remove the method for fine particle.
The utility model content
The purpose of this utility model is to fill helium pressurization major accident disposal system for a kind of nuclear power station of the not enough proposition of existing nuclear power technology.Helium is that inert gas can not react in containment, and helium has larger thermal conductivity, is beneficial to heat transfer, the formation temperature gradient fields.In the environment in certain pressure field and temperature field, utilize fine particle thermophoretic effect and turbulence effect, can the fine grained that nuclear power station produces be removed.
The nuclear power station that the utility model provides fills helium pressurization major accident disposal system, comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply, pressue device and heating apparatus, described helium source of supply links to each other with pressue device through the helium output channel, described pressue device links to each other with described heating apparatus through the lose-lose feed channel, described lose-lose feed channel is passed containment, described helium source of supply and described pressue device are arranged on outside the containment, described heating apparatus is arranged in the containment, on the described heating apparatus blow line is installed;
Described containment wall cooling system comprises: spray water tank, spray drives structure, upper spray nozzle and lower spray nozzle.
Described helium output channel is provided with valve.
Containment is inside and outside on described lose-lose feed channel the first gas pipe line all arranges electronic inhaling valve; Containment is inside and outside on the second gas pipe line all arranges non-active inhaling valve.
The electronic inhaling valve of the inside and outside setting of containment on the lose-lose feed channel; The non-active inhaling valve of the inside and outside setting of containment is that the multi-ensuring binary channels is normally moved.Inside and outside containment, all set up valve, satisfy the redundancy principles of equipment.Nuclear power single failure principle is satisfied in system's operation.
Described blow line is at least one.
Electronic valve or the non-valve that actively spurts of spurting is set on the described blow line.
Described upper spray nozzle all links to each other with described spray water tank through the spray drives structure with described lower spray nozzle.
Described upper spray nozzle and lower spray nozzle quantity all can be 200-600.
Described spray water tank is ring-type.
Described containment wall cooling system is located at the top of containment.
The described helium pressurization major accident disposal system of filling can be taked the modular mounting means, both can be installed in existing reactor when overhaul, also can be used as advanced reactor design ingredient.
The beneficial effects of the utility model are: nuclear power station fills helium pressurization major accident disposal system to have active and non-active dual system characteristics, satisfies single failure criteria, and the deposition efficiency of fine particle is high.
All types of nuclear power stations of each generation can be installed by this system.Especially to PM
10, PM
2.5Remove important using value Deng fine particle, can effectively reduce the discharge capacity of fine particle, reach the purpose of protection public health and environment.This device has safety, efficient, reliable, and it is convenient to implement, and control is simple, but the characteristics such as modularization assembling.
When major accident appearred in nuclear power station, this device filled with pressurized helium in containment; Simultaneously, to containment outer wall spray, to reduce the containment wall temperature.This kind infant industry dust arrester, as thermal source, the outer water-cooled of containment is low-temperature receiver, forms the mixed gas temperature field that has thermograde in containment with the accident high-temperature gas mixture.Utilize thermophoretic effect and turbulence effect, effectively remove the radioactivity fine grained that major accident produces.Also impel simultaneously the containment decrease temperature and pressure, to alleviate the harm of nuclear power major accident.This major accident disposal system can adopt the modular mode, is installed on inside and outside the nuclear power plant containment shell.This System Implementation is convenient, control is simple, can ensure the operation of nuclear plant safety high efficient and reliable.The nuclear power station that the utility model proposes fills helium pressurization major accident disposal system, can be applied to all types of nuclear reactors of each generation.This system can effectively remove fine particle, to guaranteeing nuclear power station surrounding environment safety and public health important value is arranged.
Description of drawings
Fig. 1 is that nuclear power station fills helium pressurization major accident disposal system synoptic diagram;
Number in the figure:
1-helium source of supply; The 2-valve; 3-helium conveyance conduit; The 4-pressue device; The outer electronic inhaling valve of containment on 5-the first gas pipe line; Electronic inhaling valve in the containment on 6-the first gas pipe line; The outer non-active inhaling valve of containment on 7-the second gas pipe line; Non-active inhaling valve in the containment on 8-the second gas pipe line; 9-the first gas pipe line; 10-the second gas pipe line; The 11-heating apparatus; The electronic valve that spurts of 12-; The non-valve that actively spurts of 13-; 14-the first blow line; 15-the second blow line; The 16-containment; First time spray nozzle of 17-; Second time spray nozzle of 18-; 19-sprays drives structure; 20-sprays water tank; Spray nozzle on the 21-first; Spray nozzle on the 22-second.
Embodiment
The following examples and accompanying drawing can make those skilled in the art more fully understand the utility model, but limit never in any form the utility model.
Embodiment 1
Nuclear power station fills helium pressurization major accident disposal system, comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply 1, pressue device 4 and heating apparatus 11, described helium source of supply 1 links to each other with pressue device 4 through helium output channel 3, described pressue device 4 links to each other with described heating apparatus 11 through the lose-lose feed channel, described lose-lose feed channel is passed containment 16, described helium source of supply 1 and described pressue device 4 are arranged on outside the containment 16, described heating apparatus 11 is arranged in the containment 16, on the described heating apparatus 11 blow line is installed;
Described containment wall cooling system comprises: spray water tank 20, spray drives structure 19, upper spray nozzle and lower spray nozzle.
Described helium output channel 3 is provided with valve 2.
Containment is inside and outside on described lose-lose feed channel the first gas pipe line 9 all arranges electronic inhaling valve; Containment is inside and outside on the second gas pipe line 10 all arranges non-active inhaling valve.
Described blow line is two, electronic spurting is set on the first blow line 14 the non-valve 13 that actively spurts is set on valve 12, the second blow lines 15.
Described upper spray nozzle all links to each other with described spray water tank 20 through spray drives structure 19 with described lower spray nozzle.
Described spray water tank is ring-type.
Described containment wall cooling system is located at the top of containment.
The structure that nuclear power station fills helium pressurization major accident disposal system Fine Particles device as shown in Figure 1.Helium is by helium source of supply 1 supply helium.During the nuclear power major accident, valve 2 is opened on the helium output channel 3, and helium enters pressue device 4 thus, pressurizes; On the first gas pipe line on the outer electronic inhaling valve 5 of containment and the first gas pipe line in the containment electronic inhaling valve 6 open the first gas pipe line 9, or on the outer non-active inhaling valve 7 of the second containment on the gas pipe line and the second gas pipe line in the containment non-active inhaling valve 8 automatically open the second gas pipe lines 10, helium is delivered to heating apparatus 11 by pressue device 4 by the first gas pipe line 9 or the second gas pipe line 10, injects in the containment; 11 pairs of high-pressure heliums of heating apparatus are heated, and heating apparatus 11 is take the accident high-temperature gas mixture as thermal source; At this moment, the electronic valve 12 that spurts is opened the first blow line 14, or the non-valve 13 that actively spurts is opened the second blow line 15 automatically, helium is discharged in the containment 16 by the first blow line 14 or the second blow line 15 from heating apparatus 11, is entered in the containment by the input helium and mixes with other gases in the containment.Simultaneously, containment utilizes spray drives structure 19 to the cooling of containment outer wall outward, and the water source of spraying component is from ring-type spray water tank 20.Spraying component sprays water-cooled cooling by upper spray nozzle and lower spray nozzle to containment top cover and tube wall.According to different reactor types, set up respectively 200-600 up and down spray nozzle, to increase the effect of spray water-cooled.Only list in the drawings on first time spray nozzle 17, the second time spray nozzle 18, first spray nozzle 22 on the spray nozzle 21, second.Form like this temperature gradient field under the certain pressure in containment, fine grained is done turbulent flow and thermophoresis campaign therein, efficiently deposits in the containment, thereby avoids radioactive grain to leak.
Related pressue device 4 is exactly inputting containment 16 from helium helium source of supply 1, that have certain pressure.
Related heating apparatus 11 is to helium rising temperature, and in the temperature, the intensification helium forms the uniform temperature gradient to containment 6 interior gas temperatures with wall in the cooling containment.
Electronic inhaling valve 6 in the containment on the outer electronic inhaling valve 5 of containment, the first gas pipe line on related the first gas pipe line, electronic non-active inhaling valve 8, the non-valve 13 that actively spurts of spurting on valve 12, the second gas pipe line on the outer non-active inhaling valve 7 of containment, the second gas pipe line in the containment are by electronic and non-active the first gas pipe line 9 or the second gas pipe line 10, the first blow line 14 or 15 two kinds of its operation functions of different path implements of the second blow line.Simultaneously, guarantee that containment can close after passing into a certain amount of helium, too high to avoid piling internal pressure.Satisfy nuclear safety single failure principle.
Related lower spray nozzle, spray drives structure 19, ring-type spray water tank 20, upper spray nozzle are that the containment outer wall is lowered the temperature, to realize the formation of temperature gradient field in the containment.
The above; it only is the better embodiment of the utility model; but protection domain of the present utility model is not limited to this; anyly be familiar with those skilled in the art in the technical scope that the utility model discloses; the variation that can expect easily or replacement all should be encompassed within the protection domain of the present utility model.Therefore, protection domain of the present utility model should be as the criterion with the protection domain of claim.
Claims (9)
1. a nuclear power station fills helium pressurization major accident disposal system, it is characterized in that: this nuclear power station fills helium pressurization major accident disposal system and comprises two parts: fill helium pressure-flow system and containment wall cooling system;
The described helium pressure-flow system that fills comprises helium source of supply (1), pressue device (4) and heating apparatus (11), described helium source of supply (1) links to each other with pressue device (4) through helium output channel (3), described pressue device (4) links to each other with described heating apparatus (11) through the lose-lose feed channel, described lose-lose feed channel is passed containment (16), described helium source of supply (1) and described pressue device (4) are arranged on outside the containment (16), described heating apparatus (11) is arranged in the containment (16), and described heating apparatus is equipped with blow line on (11);
Described containment wall cooling system comprises: spray water tank (20), spray drives structure (19), upper spray nozzle and lower spray nozzle.
2. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, and it is characterized in that: described helium output channel (3) is provided with valve (2).
3. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, it is characterized in that: containment is inside and outside on described lose-lose feed channel the first gas pipe line all arranges electronic inhaling valve; Containment is inside and outside on the second gas pipe line all arranges non-active inhaling valve.
4. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, and it is characterized in that: described blow line is at least one.
5. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, it is characterized in that: electronic valve (12) or the non-valve (13) that actively spurts of spurting is set on the described blow line.
6. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, and it is characterized in that: described upper spray nozzle all links to each other with described spray water tank (20) through spray drives structure (19) with described lower spray nozzle.
7. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, and it is characterized in that: described upper spray nozzle and lower spray nozzle quantity are 200-600.
8. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, and it is characterized in that: described spray water tank is ring-type.
9. nuclear power station according to claim 1 fills helium pressurization major accident disposal system, it is characterized in that: described containment wall cooling system is located at the top of containment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204288550U CN202771811U (en) | 2012-08-27 | 2012-08-27 | Serious accident processing system capable of charging helium and pressurizing for nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204288550U CN202771811U (en) | 2012-08-27 | 2012-08-27 | Serious accident processing system capable of charging helium and pressurizing for nuclear power station |
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| Publication Number | Publication Date |
|---|---|
| CN202771811U true CN202771811U (en) | 2013-03-06 |
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ID=47778367
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012204288550U Expired - Fee Related CN202771811U (en) | 2012-08-27 | 2012-08-27 | Serious accident processing system capable of charging helium and pressurizing for nuclear power station |
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|---|---|
| CN (1) | CN202771811U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102842346A (en) * | 2012-08-27 | 2012-12-26 | 华北电力大学 | System for processing serious accidents caused by helium pressurization in nuclear power plant |
-
2012
- 2012-08-27 CN CN2012204288550U patent/CN202771811U/en not_active Expired - Fee Related
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102842346A (en) * | 2012-08-27 | 2012-12-26 | 华北电力大学 | System for processing serious accidents caused by helium pressurization in nuclear power plant |
| CN102842346B (en) * | 2012-08-27 | 2015-02-25 | 华北电力大学 | System for processing serious accidents caused by helium pressurization in nuclear power plant |
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| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20130306 Termination date: 20130827 |