CN103474107A - Comprehensive protection device of nuclear reactor container - Google Patents
Comprehensive protection device of nuclear reactor container Download PDFInfo
- Publication number
- CN103474107A CN103474107A CN2012101866106A CN201210186610A CN103474107A CN 103474107 A CN103474107 A CN 103474107A CN 2012101866106 A CN2012101866106 A CN 2012101866106A CN 201210186610 A CN201210186610 A CN 201210186610A CN 103474107 A CN103474107 A CN 103474107A
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- insulation layer
- nuclear reactor
- heat insulation
- protection device
- comprehensive protection
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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 belongs 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 container under the accident condition, and the reactor safety is improved. The main shielding adopts a 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 invention belongs to and a kind ofly can guarantee the device that reactor vessel can be directly cooled when having an accident for providing heat insulation in nuclear reactor and preventing the protection that neutron flows out, be specifically related to a kind of nuclear reactor vessel comprehensive protector simultaneously.
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 maintain system thermal efficiency, in the reactor vessel outside, be provided with thermofin.And, if under accident conditions direct cooled reactor container, can reduce the probability that it is fused, improve the security of reactor, thereby need a kind of equipment, can be immersed in reactor vessel in cold water, and can guarantee that the steam produced can be discharged from.
Summary of the invention
The purpose of this invention is to provide a kind of raising nuclear reactor safety, simultaneously the nuclear reactor vessel comprehensive protector of barrier neutron leakage and radiation heat release.
The present invention realizes 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 heat-insulation layer; the outside of heat-insulation layer is provided with shielding construction, also has certain gap between heat-insulation layer and shielding construction.
Described shielding construction comprises water shielding tank, is full of water in water shielding tank, and its inside is provided with cooling device.
Described shielding construction is xoncrete structure.
Be provided with cooling device in described shielding construction.
Advantage of the present invention is that its structure is more succinct, is conducive under normal circumstances control radioactive leakage, under accident conditions, can, for reactor vessel provides directly cooling, improve nuclear reactor safety.Main shield adopts the metal water composite structure, 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, controls the release of reactor core fused mass.
The accompanying drawing explanation
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 present invention.
In 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 present invention is described in detail.
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; there is certain gap between pressure vessel 1 and 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 takes away from the top in gap the heat produced accident process; the outside of heat-insulation layer 2 is provided with shielding construction 3; also have certain gap between heat-insulation layer 2 and 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 2, shielding construction 3 comprises water shielding tank 8, in water shielding tank 8, is full of water, 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 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 does not occur, the air between pressure vessel 1 and shielding construction 3 in space is 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 shielding construction 3 is derived by the cooling system be arranged on wherein, these characteristics are with using cooling-air to carry out cooling method difference to shielding construction 3 in traditional nuclear power plant, thereby without the structure that cooling-air is isolated with reactor vessel is set, simplify the structure, also be easy to thermodynamic barrier is carried out to supporting and location.
When described major accident occurs, for the cooling medium that soaks pressure vessel, from the container below, import, cooling medium upwards flows and floods and the cooling pressure container, and the cooling medium that has absorbed heat continues flow upward and be discharged from.
Pressure vessels is with steel structure support, and supporting construction can be arranged on peripheral shielding construction, also can independently arrange, and is set directly on factory building pedestal or floor.
Claims (4)
1. a 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; there is certain gap between pressure vessel (1) and heat-insulation layer (2); the outside of heat-insulation layer (2) is provided with shielding construction (3), between heat-insulation layer (2) and shielding construction (3), also has certain gap.
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 (6).
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 |
|---|---|---|---|
| CN2012101866106A CN103474107A (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 |
|---|---|---|---|
| CN2012101866106A CN103474107A (en) | 2012-06-08 | 2012-06-08 | Comprehensive protection device of nuclear reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN103474107A true CN103474107A (en) | 2013-12-25 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012101866106A Pending CN103474107A (en) | 2012-06-08 | 2012-06-08 | Comprehensive protection device of nuclear reactor container |
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| CN (1) | CN103474107A (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299657A (en) * | 2014-09-09 | 2015-01-21 | 张志雄 | Nuclear reactor clamping ring zinc alloy cerium oxide high-pressure cooling system |
| CN105719706A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small reactor passive core cooling system |
| CN106898390A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of reactor pressure vessel supporting structure with function of shielding |
| CN108962408A (en) * | 2018-06-21 | 2018-12-07 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressure vessel cooling system based on vacuum chamber |
| CN113482144A (en) * | 2021-07-26 | 2021-10-08 | 中核能源科技有限公司 | Nuclear reactor cabin, framework mechanism and forming method thereof |
| CN114135350A (en) * | 2021-11-30 | 2022-03-04 | 中国核动力研究设计院 | Compact open air Brayton cycle system and method |
| CN114424296A (en) * | 2020-03-18 | 2022-04-29 | 艾托蒙内戈普洛耶克联合股份公司 | Nuclear reactor core melt positioning and cooling system |
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| CN202650568U (en) * | 2012-06-08 | 2013-01-02 | 中国核动力研究设计院 | Comprehensive protection device of nuclear reactor container |
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2012
- 2012-06-08 CN CN2012101866106A patent/CN103474107A/en active Pending
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1207036A (en) * | 1968-12-04 | 1970-09-30 | Babcock & Wilcox Ltd | Improvements in and relating to the heat-insulating screening of reactor pressure vessel walls |
| US3898126A (en) * | 1971-12-23 | 1975-08-05 | Siemens Ag | Reactor pressure tank |
| US3994776A (en) * | 1972-06-15 | 1976-11-30 | Siemens Aktiengesellschaft | Nuclear reactor installation |
| GB1471391A (en) * | 1974-02-26 | 1977-04-27 | Commissariat Energie Atomique | Shield structure for protecting the pressure vessel of a nuclear reactor |
| DE2732774A1 (en) * | 1977-07-20 | 1979-02-08 | Ght Hochtemperaturreak Tech | High temp. gas cooled reactor with top reflector cooling - by secondary gas flow driven by own power source |
| DE2816264B1 (en) * | 1978-04-14 | 1979-07-05 | Kraftwerk Union Ag | Nuclear reactor plant |
| CN1080770A (en) * | 1992-06-24 | 1994-01-12 | 西屋电气公司 | Nuclear reactor with polyhedral primary shield and removable vessel insulation |
| CN1193407A (en) * | 1995-07-13 | 1998-09-16 | 西屋电气公司 | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299657A (en) * | 2014-09-09 | 2015-01-21 | 张志雄 | Nuclear reactor clamping ring zinc alloy cerium oxide high-pressure cooling system |
| CN105719706A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Small reactor passive core cooling system |
| CN106898390A (en) * | 2015-12-21 | 2017-06-27 | 中国核动力研究设计院 | A kind of reactor pressure vessel supporting structure with function of shielding |
| CN106898390B (en) * | 2015-12-21 | 2018-11-02 | 中国核动力研究设计院 | A kind of reactor pressure vessel supporting structure with function of shielding |
| CN108962408A (en) * | 2018-06-21 | 2018-12-07 | 中国船舶重工集团公司第七〇九研究所 | A kind of pressure vessel cooling system based on vacuum chamber |
| CN114424296A (en) * | 2020-03-18 | 2022-04-29 | 艾托蒙内戈普洛耶克联合股份公司 | Nuclear reactor core melt positioning and cooling system |
| CN113482144A (en) * | 2021-07-26 | 2021-10-08 | 中核能源科技有限公司 | Nuclear reactor cabin, framework mechanism and forming method thereof |
| CN114135350A (en) * | 2021-11-30 | 2022-03-04 | 中国核动力研究设计院 | Compact open air Brayton cycle system and method |
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Application publication date: 20131225 |
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