CN203055477U - Flow-concentrating double flow path supercritical water cooled reactor - Google Patents
Flow-concentrating double flow path supercritical water cooled reactor Download PDFInfo
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- CN203055477U CN203055477U CN2013200624947U CN201320062494U CN203055477U CN 203055477 U CN203055477 U CN 203055477U CN 2013200624947 U CN2013200624947 U CN 2013200624947U CN 201320062494 U CN201320062494 U CN 201320062494U CN 203055477 U CN203055477 U CN 203055477U
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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
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Abstract
The utility model discloses a flow-concentrating double flow path supercritical water cooled reactor. The flow-concentrating double flow path supercritical water cooled reactor comprises a reactor pressure vessel, an outlet hot sleeve (204) and a reactor construction member arranged in the reactor pressure vessel, wherein a ring cavity and a lower cavity chamber connected with the ring cavity are formed between the reactor pressure vessel and the reactor construction member; the reactor construction member is internally provided with an upper cavity body, an outlet steam cavity, a flow-concentrating cavity and a mixing cavity body communicated with the upper cavity body, the upper cavity body is communicated with the ring cavity, and the flow-concentrating cavity is communicated with the lower cavity chamber; and the outlet hot sleeve (204) is communicated with the outlet steam cavity, the reactor pressure vessel is provided with an inlet connecting pipe (107) communicated with the ring cavity and an outlet connector pipe (103) communicated with the outlet hot sleeve (204), and the mixing cavity body and the outlet steam cavity are both communicated with the flow-concentrating cavity through a fuel assembly. With the structure, the flow-concentrating double flow path supercritical water cooled reactor provided by the utility model has the advantages that the whole structure is simple, the realization is convenient, and the risk that the safety factor is reduced due to arrangement of many flow paths is avoided because of the design of a double flow path reactor core structure.
Description
Technical field
The utility model relates to the supercritical water cold dome, specifically is collecting type double fluid journey supercritical water cold dome.
Background technology
Supercritical water cold dome (SCWR) is to be cooling medium with water, the outlet water state critical point (374 ℃, 22.1MPa) a kind of reactor on.Because operational factor is higher, takes all factors into consideration the restriction of aspects such as current material, manufacture level, the supercritical water cold dome is designed to the multipaths structure more.Supercritical water cold dome commonly used at present is designed to three flowage structures more, and the reactor axial distribution of three flowage structures is even, but complex structure, too much flow process number can make the reactor natural-circulation capacity descend, the reactor core safety coefficient reduces.
The utility model content
The purpose of this utility model is the too much and baroque defective of flow process at existing supercritical water cold dome existence, and a kind of simple in structure, the rational collecting type double fluid of flow process journey supercritical water cold dome is provided.
The purpose of this utility model is achieved through the following technical solutions: collecting type double fluid journey supercritical water cold dome, comprise reactor pressure vessel, export thermal sleeve and be arranged on the interior in-pile component of reactor pressure vessel, constitute the lower chambers of ring cavity and connection ring cavity between described reactor pressure vessel and the in-pile component, be provided with upper cavity in the described in-pile component, the outlet vapor chamber, the mixing chamber of manifold and connection upper cavity, upper cavity and ring cavity are connected, manifold and lower chambers are connected, described outlet thermal sleeve is connected with the outlet vapor chamber, described reactor pressure vessel is provided with the entrance sleeve of connecting ring cavity and the discharge coupling pipe of connecting the outlet thermal sleeve, and described mixing chamber and outlet vapor chamber are all connected by fuel assembly and manifold.The utility model is when using, after inlet water enters reactor from entrance sleeve, part water enters in the upper cavity by ring cavity, another part water enters in the manifold by ring cavity with lower chambers, enter in the upper cavity water through behind the hybrid chamber again in fuel assembly enters manifold, after having compiled the water that enters from lower chambers in the manifold, water enters in the outlet vapor chamber from the bottom to top by fuel assembly in the manifold, after in the outlet vapor chamber, compiling, mix, flow out reactor along the outlet thermal sleeve, and then the circulation of realization response reactor coolant.Wherein, the fuel assembly of connecting mixing chamber and manifold is a flow process fuel assembly, the fuel assembly of connecting outlet vapor chamber and manifold is two flow process fuel assemblies, from the entrance sleeve entry successively through to the process of manifold, distributing according to rational flow process behind the ring cavity, upper cavity, mixing chamber, as the cooling medium of moderator, the flow process fuel assembly reactor core zone of flowing through.The utility model is realized compiling of part entrance cooling medium, whole moderator and a flow process fuel assembly outlet coolant by manifold and is mixed, and realizes that by the outlet vapor chamber cooling medium of one, two flow process fuel assemblies is isolated and above-critical state goes out compiling, mix and deriving of saliva.
Described in-pile component comprises cradle cylinder body, be connected in the reactor core lower plate of cradle cylinder body lower end, the manifold housing that is connected with the reactor core lower plate, be fixed in the hold-down barrel in the cradle cylinder body, be connected in the reactor core upper plate of hold-down barrel lower end and be arranged on hold-down barrel interior bottom support casting and last coaming plate, described upper cavity is the hold-down barrel inner region of bottom support casting top, the described coaming plate of going up is connected with the reactor core upper plate with bottom support casting respectively at two ends up and down, described mixing chamber is last coaming plate, the cavity that constitutes between bottom support casting and the reactor core upper plate three, bottom support casting is provided with the discharge orifice of connecting upper cavity and mixing chamber, described outlet vapor chamber is last coaming plate, bottom support casting, the annular housing that reactor core upper plate and hold-down barrel constitute, described manifold is the cavity that constitutes between reactor core lower plate and the manifold housing, described ring cavity is the zone between the cylinder inboard wall of cradle cylinder body outer wall and reactor pressure vessel, lower chambers is the cavity that constitutes between the low head of manifold housing and reactor pressure vessel, described manifold housing is provided with the discharge orifice of connecting lower chambers and manifold, described cradle cylinder body and hold-down barrel top are equipped with circumferential perforate, and described ring cavity and upper cavity are connected by the perforate of cradle cylinder body and hold-down barrel.The water that the utility model enters when using in the upper cavity enters upper cavity from the circumferential perforate on cradle cylinder body and hold-down barrel top, and the discharge orifice from the bottom support casting enters behind the mixing chamber again in fuel assembly flows into manifold again.
The inwall of described cradle cylinder body is provided with the sealing sustained ring, and described hold-down barrel lower end is arranged on the circular gap that seals on the sealing sustained ring between hold-down barrel lower end and the cradle cylinder body.Under the effect of sealing sustained ring, can realize the isolation in inlet water and reactor core zone.
Be connected with the coaming plate forming board on the cradle cylinder body inwall between described sealing sustained ring and the reactor core lower plate.
Described fuel assembly comprises base, bottom nozzle and the sub-component that is connected with bottom nozzle with last base respectively of two ends up and down, described bottom nozzle is fixed on the reactor core lower plate and with manifold and connects, and described upward base passes the reactor core upper plate and contacts with the bottom support casting lower surface.So, the utility model compresses fuel assembly by bottom support casting when using
As preferably, the quantity of sub-component is 4 in each fuel assembly.
Be provided with independently moderator passage and coolant channel in the described sub-component.
Connect manifold and mixing chamber and the connection manifold fuel assembly required with exporting vapor chamber when using because of the utility model and all need many groups, reasonable in order to guarantee assignment of traffic, be provided with the throttling element on the passage that is positioned at fuel assembly connection manifold in the described reactor core lower plate.
Described outlet thermal sleeve one end is connected with the outlet vapor chamber after radially passing cradle cylinder body, hold-down barrel successively, and its other end is connected with thermal sleeve push-tight mechanism.The utility model is by setting up thermal sleeve push-tight mechanism, so can utilize thermal sleeve push-tight mechanism's inner spring and helicitic texture control outlet thermal sleeve and hold-down barrel push-tight, separate and multiple dress.
Be pressed on the hold-down barrel under the top cover of described reactor pressure vessel, and be provided with holddown spring between hold-down barrel and the top cover.The utility model so can be realized compressing in-pile component and fuel assembly by the snap-in force that top cover provides by setting up holddown spring.
Compared with prior art, the utlity model has following beneficial effect: the design of (1) in-pile component of the present utility model has realized the double-current journey circulate coolant in the supercritical water cold dome, provide rational flow process and flow field to distribute, because of the area decreases that integral body is flowed through, structure of the present utility model like this also can obtain simplifying.
(2) the utility model saliva and flows out through the discharge coupling pipe behind the outlet thermal sleeve again when using, going out saliva can not contact with the cylinder inboard wall of reactor pressure vessel, and then make reactor pressure vessel to carry out design on the basis of current material, save cost.
Description of drawings
Fig. 1 is the structural representation of the utility model embodiment;
Structural representation when Fig. 2 has the fluid circulation for embodiment of the present utility model.
The corresponding name of Reference numeral is called in the accompanying drawing: 101, top cover, 102, the top cylindrical shell, 103, the discharge coupling pipe, 104, reactor core section cylindrical shell, 105, low head, 106, the control rod drive mechanisms (CRD) base, 107, entrance sleeve, 108, thermal sleeve push-tight mechanism, 201, upper support plate, 202, throttling element, 203, the manifold housing, 204, the outlet thermal sleeve, 205, the compression spring, 206, cradle cylinder body, 207, the reactor core lower plate, 208, the coaming plate forming board, 209, the sealing sustained ring, 210, hold-down barrel, 211, the reactor core upper plate, 212, bottom support casting, 213, last coaming plate, 214, the control rod guidance set, 301, last base, 302, sub-component, 303, bottom nozzle.
Embodiment
The utility model is described in further detail below in conjunction with embodiment and accompanying drawing, but embodiment of the present utility model is not limited thereto.
Embodiment:
As shown in Figures 1 and 2, collecting type double fluid journey supercritical water cold dome, comprise reactor pressure vessel, outlet thermal sleeve 204 and be arranged on the interior in-pile component of reactor pressure vessel, wherein, the reactor pressure vessel overall geometry is similar to traditional pressurized water type reactor pressure vessel, is made up of top cover 101, top cylindrical shell 102, reactor core section cylindrical shell 104 and low head 105.Wherein, be furnished with some control rod drive mechanisms (CRD) bases 106 on the top cover 101.In-pile component comprises cradle cylinder body 206, control rod guidance set 214, is connected in the reactor core lower plate 207 of cradle cylinder body 206 lower ends, the manifold housing 203 that is connected with reactor core lower plate 207, be fixed in hold-down barrel 210 in the cradle cylinder body 206, be connected in the reactor core upper plate 211 of hold-down barrel 210 lower ends and be arranged on bottom support casting 212 and last coaming plate 213 in the hold-down barrel 210.Hold-down barrel 210 inner regions of bottom support casting 212 tops constitute upper cavity, last coaming plate is connected with reactor core upper plate 211 with bottom support casting 212 respectively at two ends about in the of 213, the cavity that constitutes between last coaming plate 213, bottom support casting 212 and reactor core upper plate 211 threes is mixing chamber, and bottom support casting 212 is provided with the discharge orifice of connecting upper cavity and mixing chamber.The annular housing that last coaming plate 213, bottom support casting 212, reactor core upper plate 211 and hold-down barrel 210 4 constitute is the outlet vapor chamber, and the cavity that constitutes between reactor core lower plate 207 and the manifold housing 203 is manifold.Zone between the cylinder inboard wall of cradle cylinder body 206 outer walls and reactor pressure vessel forms ring cavity, the cavity that constitutes between the low head 105 of manifold housing 203 and reactor pressure vessel is lower chambers, ring cavity and lower chambers are connected, manifold housing 203 is provided with the discharge orifice of connecting lower chambers and manifold, cradle cylinder body 206 and hold-down barrel 210 both tops are equipped with circumferential perforate, and ring cavity and upper cavity are connected by both perforates of cradle cylinder body 206 and hold-down barrel 210.The top cover of reactor pressure vessel is pressed on the hold-down barrel 210 for 101 times, and is provided with holddown spring 205 between hold-down barrel 210 and the top cover 101.As preferably, the zone that top cover 101 presses down hold-down barrel 210 is annular region, and holddown spring 205 is the Z-shaped spring structure of ring-type.Also be provided with the upper support plate 201 that is connected and is positioned at bottom support casting 212 tops with its inwall in the hold-down barrel 210, upper support plate 201 also is provided with the discharge orifice, and control rod guidance set 214 is realized the location by upper support plate 215 and bottom support casting 212.
Outlet thermal sleeve 204 1 ends radially pass cradle cylinder body 206 successively, hold-down barrel 210 backs are connected with the outlet vapor chamber, and its other end is connected with thermal sleeve push-tight mechanism 108.For the enhanced leaktightness performance, outlet thermal sleeve 204 cooperates with perforate on the hold-down barrel 210 and relies on the sealing ring realization to seal.The top cylindrical shell 102 of reactor pressure vessel is provided with the entrance sleeve 107 of connecting ring cavity and the discharge coupling pipe 103 of connecting outlet thermal sleeve 204.
The inwall of cradle cylinder body 206 is provided with sealing sustained ring 209, and hold-down barrel 210 lower ends are arranged on the circular gap that seals on the sealing sustained ring 209 between hold-down barrel 210 lower ends and the cradle cylinder body 206.In order to reduce reactor core to the influence of reactor pressure vessel irradiation, be connected with coaming plate forming board 208 on cradle cylinder body 206 inwalls between sealing sustained ring 209 and the reactor core lower plate 207, and then can carry out certain isolation by the fuel assembly radiation in 208 pairs of heaps of coaming plate forming board.
Mixing chamber and outlet vapor chamber are all connected by fuel assembly and manifold, fuel assembly comprises base 301, bottom nozzle 303 and the sub-component 302 that is connected with bottom nozzle 303 with last base 301 respectively of two ends up and down, bottom nozzle 301 is fixed on the reactor core lower plate 207 and with manifold and connects, and last base 303 passes reactor core upper plate 211 and contacts with bottom support casting 212 lower surfaces.Wherein, last base 301 sidepieces have window, as the outlet of entrance or the two flow process fuel assembly cooling mediums of a flow process fuel assembly cooling medium.As preferably, the quantity of sub-component 302 is 4 in each fuel assembly, and is provided with independently moderator passage and coolant channel in each sub-component 302.In order to make assignment of traffic even, be provided with the throttling element 202 on the passage that is positioned at fuel assembly connection manifold in the reactor core lower plate 207.
Above content be in conjunction with concrete preferred implementation to further describing that the utility model is done, can not assert that embodiment of the present utility model is confined to these explanations.For the utility model person of an ordinary skill in the technical field, not breaking away from other embodiments that draw under the technical solution of the utility model, all should be included in the protection domain of the present utility model.
Claims (10)
1. collecting type double fluid journey supercritical water cold dome, it is characterized in that: comprise reactor pressure vessel, export thermal sleeve (204) and be arranged on the interior in-pile component of reactor pressure vessel, constitute the lower chambers of ring cavity and connection ring cavity between described reactor pressure vessel and the in-pile component, be provided with upper cavity in the described in-pile component, the outlet vapor chamber, the mixing chamber of manifold and connection upper cavity, upper cavity and ring cavity are connected, manifold and lower chambers are connected, described outlet thermal sleeve (204) is connected with the outlet vapor chamber, described reactor pressure vessel is provided with the entrance sleeve (107) of connecting ring cavity and the discharge coupling pipe (103) of connecting outlet thermal sleeve (204), and described mixing chamber and outlet vapor chamber are all connected by fuel assembly and manifold.
2. collecting type according to claim 1 double fluid journey supercritical water cold dome, it is characterized in that: described in-pile component comprises cradle cylinder body (206), be connected in the reactor core lower plate (207) of cradle cylinder body (206) lower end, the manifold housing (203) that is connected with reactor core lower plate (207), be fixed in the hold-down barrel (210) in the cradle cylinder body (206), be connected in the reactor core upper plate (211) of hold-down barrel (210) lower end and be arranged on hold-down barrel (210) interior bottom support casting (212) and last coaming plate (213), described upper cavity is hold-down barrel (210) inner region of bottom support casting (212) top, the described coaming plate (213) of going up is connected with reactor core upper plate (211) with bottom support casting (212) respectively at two ends up and down, described mixing chamber is last coaming plate (213), the cavity that constitutes between bottom support casting (212) and reactor core upper plate (211) three, bottom support casting (212) is provided with the discharge orifice of connecting upper cavity and mixing chamber, described outlet vapor chamber is last coaming plate (213), bottom support casting (212), the annular housing that reactor core upper plate (211) and hold-down barrel (210) four constitute, described manifold is the cavity that constitutes between reactor core lower plate (207) and the manifold housing (203), described ring cavity is the zone between the cylinder inboard wall of cradle cylinder body (206) outer wall and reactor pressure vessel, lower chambers is the cavity that constitutes between the low head (105) of manifold housing (203) and reactor pressure vessel, described manifold housing (203) is provided with the discharge orifice of connecting lower chambers and manifold, described cradle cylinder body (206) and both tops of hold-down barrel (210) are equipped with circumferential perforate, and described ring cavity and upper cavity are connected by cradle cylinder body (206) and both perforates of hold-down barrel (210).
3. collecting type according to claim 2 double fluid journey supercritical water cold dome, it is characterized in that: the inwall of described cradle cylinder body (206) is provided with sealing sustained ring (209), and described hold-down barrel (210) lower end is arranged on the circular gap that seals on the sealing sustained ring (209) between hold-down barrel (210) lower end and the cradle cylinder body (206).
4. collecting type double fluid journey supercritical water cold dome according to claim 3 is characterized in that: be connected with coaming plate forming board (208) on cradle cylinder body (206) inwall between described sealing sustained ring (209) and the reactor core lower plate (207).
5. collecting type according to claim 2 double fluid journey supercritical water cold dome, it is characterized in that: described fuel assembly comprises base (301), bottom nozzle (303) and the sub-component (302) that is connected with bottom nozzle (303) with last base (301) respectively of two ends up and down, the reactor core lower plate (207) that is fixed on described bottom nozzle (301) goes up and connects with manifold, and described upward base (303) passes reactor core upper plate (211) and contacts with bottom support casting (212) lower surface.
6. collecting type according to claim 5 double fluid journey supercritical water cold dome, it is characterized in that: the quantity of sub-component in each fuel assembly (302) is 4.
7. collecting type double fluid journey supercritical water cold dome according to claim 5 is characterized in that: be provided with independently moderator passage and coolant channel in the described sub-component (302).
8. collecting type double fluid journey supercritical water cold dome according to claim 5 is characterized in that: be provided with the throttling element (202) on the passage that is positioned at fuel assembly connection manifold in the described reactor core lower plate (207).
9. according to any described collecting type double fluid journey supercritical water cold dome in the claim 2～8, it is characterized in that: described outlet thermal sleeve (204) one ends radially pass cradle cylinder body (206) successively, hold-down barrel (210) back is connected with the outlet vapor chamber, and its other end is connected with thermal sleeve push-tight mechanism (108).
10. according to any described collecting type double fluid journey supercritical water cold dome in the claim 2～8, it is characterized in that: be pressed under the top cover of described reactor pressure vessel (101) on the hold-down barrel (210), and be provided with holddown spring (205) between hold-down barrel (210) and the top cover (101).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200624947U CN203055477U (en) | 2013-02-04 | 2013-02-04 | Flow-concentrating double flow path supercritical water cooled reactor |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2013200624947U CN203055477U (en) | 2013-02-04 | 2013-02-04 | Flow-concentrating double flow path supercritical water cooled reactor |
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| CN203055477U true CN203055477U (en) | 2013-07-10 |
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| CN2013200624947U Withdrawn - After Issue CN203055477U (en) | 2013-02-04 | 2013-02-04 | Flow-concentrating double flow path supercritical water cooled reactor |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103106932A (en) * | 2013-02-04 | 2013-05-15 | 中国核动力研究设计院 | Flow-concentrating type two-flow super-critical water-cooled reactor |
| CN104658619A (en) * | 2015-02-11 | 2015-05-27 | 中国科学院合肥物质科学研究院 | Inherent safety protection method of fast neutron zero power device under flooding severe accident |
| CN109036604A (en) * | 2018-07-20 | 2018-12-18 | 中广核研究院有限公司 | A kind of novel reactor core filter device |
| CN114382829A (en) * | 2022-01-10 | 2022-04-22 | 中广核工程有限公司 | Instrument guide assembly compresses tightly damping mechanism |
-
2013
- 2013-02-04 CN CN2013200624947U patent/CN203055477U/en not_active Withdrawn - After Issue
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103106932A (en) * | 2013-02-04 | 2013-05-15 | 中国核动力研究设计院 | Flow-concentrating type two-flow super-critical water-cooled reactor |
| CN103106932B (en) * | 2013-02-04 | 2015-12-30 | 中国核动力研究设计院 | Collecting type double-flow Supercritical-Pressure Light Water Cooled Reactor |
| CN104658619A (en) * | 2015-02-11 | 2015-05-27 | 中国科学院合肥物质科学研究院 | Inherent safety protection method of fast neutron zero power device under flooding severe accident |
| CN109036604A (en) * | 2018-07-20 | 2018-12-18 | 中广核研究院有限公司 | A kind of novel reactor core filter device |
| CN109036604B (en) * | 2018-07-20 | 2024-01-16 | 中广核研究院有限公司 | Reactor core filtering device |
| CN114382829A (en) * | 2022-01-10 | 2022-04-22 | 中广核工程有限公司 | Instrument guide assembly compresses tightly damping mechanism |
| CN114382829B (en) * | 2022-01-10 | 2023-07-04 | 中广核工程有限公司 | Instrument guide assembly compacting vibration reduction mechanism |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20130710 Effective date of abandoning: 20151230 |
|
| C25 | Abandonment of patent right or utility model to avoid double patenting |