CN203055475U - Reactor core fluid outlet thermal sleeve structure of supercritical water cooled reactor - Google Patents
Reactor core fluid outlet thermal sleeve structure of supercritical water cooled reactor Download PDFInfo
- Publication number
- CN203055475U CN203055475U CN2013200626548U CN201320062654U CN203055475U CN 203055475 U CN203055475 U CN 203055475U CN 2013200626548 U CN2013200626548 U CN 2013200626548U CN 201320062654 U CN201320062654 U CN 201320062654U CN 203055475 U CN203055475 U CN 203055475U
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- thermal sleeve
- reactor
- supercritical water
- reactor core
- outlet
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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 provides a reactor core fluid outlet thermal sleeve structure of a supercritical water cooled reactor. The reactor core fluid outlet thermal sleeve structure comprises a thermal sleeve and an in-reactor sealing ring, wherein an opening is formed at one end of the thermal sleeve; the in-reactor sealing ring is arranged on the outer surface of the opening end of the thermal sleeve; the other end of the thermal sleeve is closed; a fluid outlet corresponding to an outlet connection pipe of a pressure container is formed in the pipe wall, which is close to the closed side, of the thermal sleeve; a check ring is arranged on the outer wall between the opening end and the fluid outlet of the thermal sleeve; an outlet section sealing ring is arranged on the check ring; a push tightening mechanism is connected to the closed end of the thermal sleeve; and the thermal sleeve is in a round-pipe shape. Due to the reactor core fluid outlet thermal sleeve structure, fluid at the outlet of the reactor can be well sealed, so that a phenomenon that high-temperature fluid is in direct contact with the inner wall of the pressure container of the reactor because of fluid leakage is avoided.
Description
Technical field
The utility model relates to a kind of nuclear reactor in-pile component, specifically is a kind of nuclear reactor fluid egress point thermal sleeve structure, is particularly useful for the higher heap type of reactor core fluid outlet temperature, as the supercritical water cold dome.
Background technology
Present pressurized water type nuclear-power reactor, its working temperature and working pressure lower (temperature is generally less than 300 ℃, pressure and is generally less than 20MPa), reactor core fluid egress point nozzle arrangement has adopted heat expansion type exit seal scheme (seeing accompanying drawing 1) to realize exporting the sealing of fluid.The ultimate principle of sealing structure is to utilize the in-pile component material different with the pressure vessel material linear expansion coefficient, when temperature variation, the heat expansion that causes the two is poor, realizes hanging basket outlet ozzle and pressure vessel outlet boss clearance fit, the hot sealing of fitting down under cold conditions.
Because above-mentioned design utilization is that the linear expansion coefficient of storeroom is poor, therefore, in the reactor actual motion, can not realize sealing completely, there is certain leakage current amount all the time in the discharge connection place.For traditional pressurized water type reactor, because running environment is not harsh, the outlet coolant temperature of leakage current is lower than the design temperature of pressure vessel, therefore, as long as the leakage current amount all can be accepted in the scope of thermal-hydraulic and safety analysis permission.And as the 4th generation one of reactor type the supercritical water cold dome, compare with the pressurized water type reactor, its working temperature, working pressure all have larger difference, supercritical water cold dome outlet fluid state is (374 ℃ of its critical points, 22.1MPa) on, in the supercritical water cold dome design proposal of reality, the temperature of outlet coolant is often more than 500 ℃, far above the outlet fluid temperature (F.T.) of pressurized water type reactor.Therefore, as continuing to adopt the heat expansion type exit seal scheme of existing presurized water reactor, the high temperature leakage current that the discharge connection place produces will directly contact with pressure vessel inside, can not satisfy reactor core thermal-hydraulic and safety requirements under supercritical water cold dome running environment.
The utility model content
The utility model is at the defective of prior art, provide a kind of be applicable to supercritical water cold dome running environment, can realize the derivation of above-critical state outlet fluid in the reactor, realize the excellent sealing of core exit fluid, prevent the reactor core fluid egress point thermal sleeve structure that outlet coolant and reactor pressure vessel inwall directly contact.
The utility model is achieved through the following technical solutions:
Supercritical water cold dome reactor core fluid egress point thermal sleeve structure comprises thermal sleeve, heap inner seal ring, thermal sleeve one end opening, and the heap inner seal ring is installed on the thermal sleeve openend outside surface, the sealing of the thermal sleeve other end.Arranging of inner seal ring of heap guaranteed sealing good between thermal sleeve openend and the reactor hanging basket, prevents the leakage current phenomenon and causes high temperature fluid directly to contact with the reactor pressure vessel inwall.
Described thermal sleeve is provided with the fluid egress point corresponding with the pressure vessel outlet adapter near the tube wall of closed side.The setting of opening and pressure vessel outlet are taken over corresponding, can realize the derivation of above-critical state outlet fluid in the reactor, and the outlet fluid flows out through this, enters trunk line.
On the outer wall between openend and the fluid egress point, also be provided with baffle ring at described thermal sleeve, the outlet section sealing ring is installed on the baffle ring.The baffle ring that arranges on baffle ring on the thermal sleeve outer wall and the pressure vessel outlet section is corresponding, the outlet section sealing ring is arranged between two baffle rings, realize excellent sealing, avoided exporting fluid and directly contact with the pressure vessel inwall, guaranteed the isolation of outlet coolant and pressure vessel inwall.
Also be connected with push-tight mechanism on the blind end of described thermal sleeve.The arranging of push-tight mechanism realize supercritical water cold dome outlet thermal sleeve structure and in-pile component propelling, separate and multiple dress.
Described thermal sleeve is the pipe shape.
Figure of description
Fig. 1 supercritical water cold dome reactor core fluid egress point thermal sleeve structural representation
Description of drawings
In the drawings: the 1-thermal sleeve, 2-piles inner seal ring, 3-outlet section sealing ring, 4-cradle cylinder body, 5-hold-down barrel, 6-container outlet section, 7-pressure vessel, 8-push-tight mechanism, 9-fluid egress point
Embodiment
Below in conjunction with accompanying drawing and embodiment, further introduce with regard to a kind of supercritical water cold dome reactor core fluid egress point thermal sleeve structure that the utility model provides:
As shown in Figure 1, supercritical water cold dome reactor core fluid egress point thermal sleeve structure, comprise thermal sleeve 1, heap inner seal ring 2, thermal sleeve 1 one end openings, openend radially pushes, pass the perforate on the cradle cylinder body 4 in the reactor pressure vessel, cooperate with the perforate on the hold-down barrel 5, heap inner seal ring 2 be installed in thermal sleeve openend outside surface, with surface of contact that hold-down barrel 5 cooperates on, realize the sealing between thermal sleeve openend and the hold-down barrel 5 thus, thereby realize the sealing of reactor core fluid when flowing out hold-down barrel 5, inflow thermal sleeve 1.
Described thermal sleeve 1 other end sealing, tube wall in described thermal sleeve 1 close closed side is provided with pressure vessel outlet takes over corresponding fluid egress point 9, the setting of fluid egress point 9 is corresponding with pressure vessel 7 discharge connections, can realize the derivation of above-critical state outlet fluid in the reactor, the outlet fluid flows out through this, enters trunk line.
On the outer wall between openend and the fluid egress point 9, also be provided with baffle ring at described thermal sleeve 1, outlet section sealing ring 3 is installed on the baffle ring.The baffle ring that arranges on baffle ring on thermal sleeve 1 outer wall and the pressure vessel outlet section 6 is corresponding, outlet section sealing ring 3 is arranged between two baffle rings, realized excellent sealing, avoid reactor core fluid process thermal sleeve 1 when fluid outlet 9 is flowed out, produce leakage current at fluid egress point 9 places, high temperature leakage current body refluxes and directly contacts with pressure vessel 7 inwalls, thereby jeopardizes nuclear reactor safety.
Also be connected with push-tight mechanism 8 on the blind end of described thermal sleeve 1, when reactor reloading pattern need take out hanging basket, thermal sleeve 1 radially can be pulled out the perforate of cradle cylinder body 4 and hold-down barrel 5 by push-tight mechanism 8, make hanging basket remove radially constraint, successfully from reactor, take out; Reload and finish, put back to hanging basket in the reactor after, by push-tight mechanism 8 thermal sleeve 1 is pushed in the perforate of cradle cylinder body 4 and hold-down barrel 5.
Further, described thermal sleeve 1 can be the pipe shape, also can realize the hollow tubular that the reactor core fluid flows out for square, polygonal etc., is preferably the pipe shape.
The supercritical water cold dome reactor core fluid egress point thermal sleeve structure that the utility model provides, realized the multi-sealed of core exit fluid, avoided fluid to contact with the direct of pressure vessel inwall, the heat expansion type exit seal scheme that has solved existing presurized water reactor is used the problem that can not satisfy reactor core thermal-hydraulic and safety requirements in the supercritical water cold dome, improved the security of supercritical water cold dome operation, simultaneously, this version is simple, mounting or dismounting are convenient, has improved supercritical water cold dome economy.
As mentioned above, just can realize the utility model well.
Claims (5)
1. supercritical water cold dome reactor core fluid egress point thermal sleeve structure comprises thermal sleeve (1), heap inner seal ring (2), thermal sleeve (1) one end opening, and heap inner seal ring (2) is installed on the thermal sleeve openend outside surface, the sealing of thermal sleeve (1) other end.
2. supercritical water cold dome reactor core fluid egress point thermal sleeve structure as claimed in claim 1 is characterized in that: described thermal sleeve (1) is provided with pressure vessel outlet near the tube wall of closed side and takes over corresponding fluid egress point (9).
3. supercritical water cold dome reactor core fluid egress point thermal sleeve structure as claimed in claim 2, it is characterized in that: on the outer wall between openend and the fluid egress point (9), also be provided with baffle ring at described thermal sleeve (1), outlet section sealing ring (3) is installed on the baffle ring.
4. as claim 1 or 3 described supercritical water cold dome reactor core fluid egress point thermal sleeve structures, it is characterized in that: also be connected with push-tight mechanism on the blind end of described thermal sleeve (1).
5. supercritical water cold dome reactor core fluid egress point thermal sleeve structure as claimed in claim 4, it is characterized in that: described thermal sleeve (1) is the pipe shape.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200626548U CN203055475U (en) | 2013-02-04 | 2013-02-04 | Reactor core fluid outlet thermal sleeve structure of supercritical water cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200626548U CN203055475U (en) | 2013-02-04 | 2013-02-04 | Reactor core fluid outlet thermal sleeve structure of supercritical water cooled reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203055475U true CN203055475U (en) | 2013-07-10 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2013200626548U Expired - Lifetime CN203055475U (en) | 2013-02-04 | 2013-02-04 | Reactor core fluid outlet thermal sleeve structure of supercritical water cooled reactor |
Country Status (1)
| Country | Link |
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| CN (1) | CN203055475U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105719705A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Outlet connection pipe in pressurized water reactor integral hydraulic simulation test |
| CN106935283A (en) * | 2015-11-16 | 2017-07-07 | 通用电气-日立核能美国有限责任公司 | Nuclear reactor stream sealing system and seal |
| CN114365235A (en) * | 2019-02-25 | 2022-04-15 | 西屋电气有限责任公司 | Anti-rotation arrangement for a thermal sleeve |
-
2013
- 2013-02-04 CN CN2013200626548U patent/CN203055475U/en not_active Expired - Lifetime
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105719705A (en) * | 2014-12-01 | 2016-06-29 | 上海核工程研究设计院 | Outlet connection pipe in pressurized water reactor integral hydraulic simulation test |
| CN106935283A (en) * | 2015-11-16 | 2017-07-07 | 通用电气-日立核能美国有限责任公司 | Nuclear reactor stream sealing system and seal |
| CN114365235A (en) * | 2019-02-25 | 2022-04-15 | 西屋电气有限责任公司 | Anti-rotation arrangement for a thermal sleeve |
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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 |
Granted publication date: 20130710 |
|
| CX01 | Expiry of patent term |