CN202650568U - Comprehensive protection device of nuclear reactor container - Google Patents
Comprehensive protection device of nuclear reactor container Download PDFInfo
- Publication number
- CN202650568U CN202650568U CN201220267137XU CN201220267137U CN202650568U CN 202650568 U CN202650568 U CN 202650568U CN 201220267137X U CN201220267137X U CN 201220267137XU CN 201220267137 U CN201220267137 U CN 201220267137U CN 202650568 U CN202650568 U CN 202650568U
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- CN
- China
- Prior art keywords
- insulation layer
- nuclear reactor
- heat insulation
- protection device
- comprehensive protection
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model relates to a comprehensive protection device of a nuclear reactor container. The comprehensive protection device comprises a heat insulation layer, wherein the heat insulation layer is arranged at the outer side of the pressure container, a certain gap is arranged between the pressure container and the heat insulation layer, the outer side of the heat insulation layer is provided with a shielding structure, and a certain gap is also arranged between the heat insulation layer and the shielding structure. The comprehensive protection device has the advantages that the structure is simpler and more compact, the radioactivity leakage is favorably controlled under the normal condition, the direct cooling can be provided for the nuclear reactor under the accident condition, and the reactor safety is improved. The main shielding adopts the metal water composite structure, and the metal structure is favorable for realizing the modular production and installation, wherein water has the characteristic of low cost, in addition, the additional hot trap can be provided under the serious accident condition, and the release of reactor core melts is controlled.
Description
Technical field
The utility model belongs to a kind of can guarantee the device that reactor vessel can be directly cooled simultaneously for providing heat insulation in the nuclear reactor and preventing the protection that neutron flows out when having an accident, be specifically related to a kind of nuclear reactor vessel comprehensive protector.
Background technology
The reactor vessel of nuclear reactor plant must be provided with the biological protection layer so that the radiation injury that reactor operation produces is avoided in protection personnel and peripheral region.In order to protect the biological protection layer to avoid the evil of high temperature, simultaneously in order to keep system thermal efficiency, be provided with thermofin in the reactor vessel outside.And, if under accident conditions direct cooled reactor container, can reduce it by the probability of burn through, improve the security of reactor, thereby need a kind of equipment, can be immersed in reactor vessel in the cold water, and can guarantee that the steam that produces can be discharged from.
Summary of the invention
The purpose of this utility model provides a kind of raising nuclear reactor safety, simultaneously the nuclear reactor vessel comprehensive protector of barrier neutron leakage and radiation heat release.
The utility model is to realize like this; a kind of nuclear reactor vessel comprehensive protector; it comprises the heat-insulation layer that is arranged on the pressure vessel outside; has certain gap between pressure vessel and the heat-insulation layer; the outside of heat-insulation layer is provided with shielding construction, also has certain gap between heat-insulation layer and the shielding construction.
Described shielding construction comprises water shielding tank, is full of water in the water shielding tank, and its inside is provided with cooling device.
Described shielding construction is xoncrete structure.
Be provided with cooling device in the described shielding construction.
The utility model has the advantages that, its structure is more succinct, is conducive under normal circumstances control radioactive leakage, can for reactor vessel provides direct cooling, improve nuclear reactor safety under accident conditions.The metal water composite structure is adopted in main shield, and its metal construction is conducive to realize modularization production and installation, and glassware for drinking water wherein has characteristics with low cost, and extra hot trap can be provided in the major accident situation, the release of control reactor core fused mass.
Description of drawings
Fig. 1 is existing pressurized water reactor heat-insulation layer and main shield structural representation thereof;
Fig. 2 is nuclear reactor vessel comprehensive protector structural representation provided by the utility model.
Among the figure, 1 pressure vessel, 2 heat-insulation layers, 3 shielding constructions, 4 cooling devices, 5 chilled waters, 6 steam, 7 cooling-airs, 8 water shielding tanks, 9 water.
Embodiment
Below in conjunction with the drawings and specific embodiments the utility model is elaborated.
As shown in Figure 2; it comprises the heat-insulation layer 2 that is arranged on pressure vessel 1 outside nuclear reactor vessel comprehensive protector; has certain gap between pressure vessel 1 and the heat-insulation layer 2; gap length can be determined according to concrete performance; in accident process; chilled water 5 enters from the bottom in gap; steam 6 is taken away the heat that produces the accident process from the top in gap; the outside of heat-insulation layer 2 is provided with shielding construction 3; also have certain gap between heat-insulation layer 2 and the shielding construction 3, gap length can be determined according to concrete performance.
Wherein, shielding construction 3 can have various ways, and as shown in Figure 3, shielding construction 3 comprises water shielding tank 8, is full of water in the water shielding tank 8, and section is equipped with cooling device 4 within it.Shielding construction 3 also can adopt xoncrete structure, and cooling device also can be installed in its inside.
Heat-insulation layer 2 generally can be selected the multiple materials such as heat-preservation cotton or metallic insulation.
Heat-insulation layer 2 is with leaving certain space between the pressure vessel 1, allow that introducing cooling medium under accident conditions is immersed in reactor vessel wherein, and the cryogen discharge that will absorb enough heats is gone out.When described accident did not occur, the air between pressure vessel 1 and the shielding construction 3 in the space was suppressed with the circulation of manufacturer's air, prevents radioactive diffusions such as Ar-41 of air-activated generation.
When described accident does not occur, heat in the shielding construction 3 is derived by the cooling system that is arranged on wherein, these characteristics are with using cooling-air different to the method that shielding construction 3 cools off in traditional nuclear power plant, thereby need not to arrange with cooling-air with the isolated structure of reactor vessel, simplify the structure, also be easy to thermodynamic barrier is carried out supporting and location.
When described major accident occured, the cooling medium that is used for soaking pressure vessel was from the importing of container below, and cooling medium upwards flows and floods and the cooling pressure container, and the cooling medium that has absorbed heat continues to flow upward and be discharged from.
Pressure vessels is with steel structure support, and supporting construction can be arranged on the peripheral shielding construction, also can independently arrange, and namely is set directly on factory building pedestal or the floor.
Claims (4)
1. nuclear reactor vessel comprehensive protector; it is characterized in that: it comprises the heat-insulation layer (2) that is arranged on pressure vessel (1) outside; has certain gap between pressure vessel (1) and the heat-insulation layer (2); the outside of heat-insulation layer (2) is provided with shielding construction (3), also has certain gap between heat-insulation layer (2) and the shielding construction (3).
2. a kind of nuclear reactor vessel comprehensive protector as claimed in claim 1, it is characterized in that: described shielding construction (3) comprises water shielding tank (8), and water shielding tank is full of water in (8), and its inside is provided with cooling device (4).
3. a kind of nuclear reactor vessel comprehensive protector as claimed in claim 1, it is characterized in that: described shielding construction (3) is xoncrete structure.
4. a kind of nuclear reactor vessel comprehensive protector as claimed in claim 3, it is characterized in that: described shielding construction is provided with cooling device in (3).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201220267137XU CN202650568U (en) | 2012-06-08 | 2012-06-08 | Comprehensive protection device of nuclear reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201220267137XU CN202650568U (en) | 2012-06-08 | 2012-06-08 | Comprehensive protection device of nuclear reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202650568U true CN202650568U (en) | 2013-01-02 |
Family
ID=47419636
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201220267137XU Expired - Lifetime CN202650568U (en) | 2012-06-08 | 2012-06-08 | Comprehensive protection device of nuclear reactor container |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN202650568U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103474107A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Comprehensive protection device of nuclear reactor container |
| 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 |
| 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 |
| CN111899901A (en) * | 2020-08-12 | 2020-11-06 | 中国核动力研究设计院 | Passive and active combined molten material in-pile retention cooling system |
-
2012
- 2012-06-08 CN CN201220267137XU patent/CN202650568U/en not_active Expired - Lifetime
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103474107A (en) * | 2012-06-08 | 2013-12-25 | 中国核动力研究设计院 | Comprehensive protection device of nuclear reactor container |
| 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 |
| 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 |
| 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 |
| CN111899901A (en) * | 2020-08-12 | 2020-11-06 | 中国核动力研究设计院 | Passive and active combined molten material in-pile retention cooling system |
| 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 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term | ||
| CX01 | Expiry of patent term |
Granted publication date: 20130102 |