CN204087826U - A kind of subcritical covering refuelling system - Google Patents
A kind of subcritical covering refuelling system Download PDFInfo
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- CN204087826U CN204087826U CN201420471827.6U CN201420471827U CN204087826U CN 204087826 U CN204087826 U CN 204087826U CN 201420471827 U CN201420471827 U CN 201420471827U CN 204087826 U CN204087826 U CN 204087826U
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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 kind of subcritical covering refuelling system, belong to the equipment technical field of fission fusion hybrid reactor.Subcritical covering refuelling system of the present utility model, vacuum shell is provided with 18 web joints, described web joint is formed by connecting by two symmetrical web joint module bolts, TF upper junction plate is had additional between two web joint modules of a web joint wherein, described TF upper junction plate is between two TF coils, and the web joint module of described TF upper junction plate and both sides is bolted; Described TF upper junction plate offers the dress discharge port be communicated with inside and outside vacuum shell.Subcritical covering refuelling system of the present utility model, reduces tube fluid resistance, increases the flow of single cladding modular, improves the heat-exchange capacity of the subcritical covering of ITER fission fusion hybrid reactor; Reduce the installation difficulty of cladding modular, be conducive to the maintenance in later stage, safeguard and reload.
Description
Technical field
The utility model relates to the equipment and technology of fission fusion hybrid reactor, especially a kind of subcritical covering refuelling system of fission fusion hybrid reactor based on ITER.
Background technology
ITER is a kind of magnetic trapped fusion apparatus, will continue deuterium-tritium reaction occurs when the temperature of plasma wherein and density meet Lawson criterion.In order to absorb the energy that fusion is released, and protecting vacuum shell and magnet, needing in vacuum shell, arrange one deck covering (Blanket).Covering is divided into two parts: in the face of the first wall and the shielding slab thereafter of plasma, wherein the first wall is for absorbing the ion and electronics of escaping from magnetic field, and shielding slab is for absorbing neutron.The energy of ion, electronics and neutron deposits and is taken out of vacuum chamber by covering cooling system in covering.
The main body Tokamak system rest of ITER is in cylindrical concrete biological shielding well, enter Tokamak device and have two kinds of passages: one is the port mouth of cylindrical sides upper, middle and lower three layers, be mainly used in installing each device in vacuum shell and various plasma heating, electric current drive and all kinds of detector; Two be positioned at right cylinder top coagulation earth mulch, be mainly used in the installation of various large-scale plant such as magnet and vacuum shell.The height of Port mouth and width are subject to the restriction of pole to spacing between magnet PF and circumferential magnet TF respectively, and the port mouth therefore reloaded just can only be designed to less size, are only suitable for mode that horizontal direction is transported into install the energy covering of little module.
The blanket design of ITER is the form of little module, and has reserved for it passage that reloads running through biological shielding shell, cryostat, cold screen and vacuum layer, adopts little module, and the manifold of whole covering is complicated, and flow resistance is large, and heat exchange efficiency is low; When covering reloads, because module is numerous, the overall time of reloading is increased, if any part of module structure or functional defect, all modules need be investigated one by one, add difficulty of reloading.
Utility model content
Goal of the invention of the present utility model is: for above-mentioned Problems existing, a kind of subcritical covering refuelling system of fission fusion hybrid reactor based on ITER is provided, overcome ITER little module manifold complicated, flow resistance is large, heat exchange efficiency is low, and the reload efficiency of reloading of mode of little module is low, process of reloading complexity, is difficult to the shortcoming changed to strip energy module; Reduce tube fluid resistance, increase the flow of single cladding modular, improve the heat-exchange capacity of the subcritical covering of ITER fission fusion hybrid reactor; Reduce the installation difficulty of cladding modular, be conducive to the maintenance in later stage, safeguard and reload.
The technical solution adopted in the utility model is as follows:
Subcritical covering refuelling system of the present utility model, vacuum shell is provided with 18 web joints, described web joint is formed by connecting by two symmetrical web joint module bolts, TF upper junction plate is had additional between two web joint modules of a web joint wherein, described TF upper junction plate is between two TF coils, and the web joint module of described TF upper junction plate and both sides is bolted; Described TF upper junction plate offers the dress discharge port be communicated with inside and outside vacuum shell.
Owing to have employed said structure, in order to make full use of the 14MeV neutron that fusion is released, the fission fusion hybrid reactor covering based on ITER device is equipped with fissioner, makes it be not only the such shield of ITER, but an energy sources production apparatus, be also referred to as energy covering.Energy covering is exaggerated fusion energy greatly, in order to effectively the energy be exported covering, originally the covering of little module and the design of cooling system can not meet demand, energy covering will be designed to elongate in shape, to reduce flow resistance, augmented flow, improve exchange capability of heat, reduce the difficulty of installing and changing covering, but such design cannot enter in vacuum shell by the original passage equatorial port that reloads of ITER, therefore take the upper junction plate of TF (UOIS) between two TF coils, for resisting the wind tunnel between coil, power suffered by web joint (UOIS) is very large, therefore should avoid repeating welding to it.In the design that ITER is original, have 18 web joints (UOIS), each web joint (UOIS) is divided into two symmetrical parts, is also web joint module, is connected between two parts by bolt.In order to the passage that reloads can be cleaned out, need to change one of them web joint (UOIS).Newly-designed web joint (UOIS) is sandwich structure, the middle plate that removably connects (TF upper junction plate) is bolted with the web joint module of the left and right sides, this design proposal meets the structural strength demand of web joint (UOIS), need not repeat welding simultaneously.It is complicated that the utility model overcomes ITER little module manifold, and flow resistance is large, and heat exchange efficiency is low, and the reload efficiency of reloading of mode of little module is low, and process of reloading complexity, is difficult to the shortcoming changed to strip energy module; Reduce tube fluid resistance, increase the flow of single cladding modular, improve the heat-exchange capacity of the subcritical covering of ITER fission fusion hybrid reactor; Reduce the installation difficulty of cladding modular, be conducive to the maintenance in later stage, safeguard and reload.
Subcritical covering refuelling system of the present utility model, described vacuum shell includes inside and outside two-layer, and the downside of described dress discharge port extends to internal layer, and the upside of dress discharge port extends to the upper interface of vacuum shell, and flushes with the outer attached shielding slab of former upper interface; The shielding slab arranged in the vacuum shell inside at dress discharge port place and vacuum shell match, and described shielding slab leads to upper interface with the cooling duct of dress discharge port by the sidewall filling discharge port.
Owing to have employed said structure, under the condition of not interfering with miscellaneous part, increase planimetric area as much as possible; Opening does not use the mode of welding to connect as far as possible, will ensure vacuum tightness and radiation shield simultaneously.Because vacuum shell comprises inside and outside two-layer, therefore ensure only to change internal layer or outer vacuum shell in the process expanding dress discharge port at every turn, then increase the thickness of floor between two-layer vacuum shell, reduce the impact on structural strength to greatest extent.Vacuum shell on the downside of dress discharge port only changes the vacuum shell of internal layer, would not interference like this with the outside link plate IOIS of TF; The outer attached shielding slab always expanded to former upper interface (upper port) on the upside of dress discharge port is mutually concordant, like this would not with UOIS and cold screen interference.Because dress discharge port occupies the outer attached shielding slab of upper interface (upper port), and the shield decreased between two-layer vacuum shell, therefore specialized designs shield assembly is needed, as shown in the figure, the outer of shield bottom matches just as vacuum shell, the cooling duct of shield and handling material port leads to upper interface by the sidewall of upper interface (upper port), and finally to be taken out of Tokamak(tokamak be a kind ofly utilize magnetic confinement to realize the toroidal container of controlled nuclear fusion).
Subcritical covering refuelling system of the present utility model, the top of described shielding slab is set to dress discharge port the flange face mutually mated respectively, and described shielding slab forms first at dress discharge port place by bolt and sealing ring and seals; The sheet metal seal welding arranged above described shielding slab forms second sealing on dress discharge port.
Owing to have employed said structure, the sealing of dress discharge port adopts flange seal to add welded seal, dress discharge port upper end processes an end face of flange, and shielding slab top also processes a flange face matched simultaneously, and both carry out first sealing by bolt and sealing ring.Second sealing is carried out with sheet metal by the mode of seal welding again above bolt.Ensure the vacuum tightness of vacuum chamber by two seals, simultaneously because sheet metal only plays sealing not as force structure, welding can be repeated to it.
Subcritical covering refuelling system of the present utility model, described vacuum shell is provided with carrier in the outer carrier of shell and shell, the dress discharge port place in vacuum shell is located at by the outer carrier of described shell, the outer carrier of described shell comprises rectangular housing and can fix the mechanical arm of interior surrounding layer, described housing is connected to dress discharge port place, and described mechanical arm is located in housing; In described shell, carrier comprises and is located at divertor track in vacuum shell and upper sliding shape track, on described divertor track, coupling has bottom system, the motor that described bottom system is arranged is driven through gear and coordinates with divertor track and provide power, on described sliding shape track, coupling has upper system, described upper system is provided with welding robot, be connected by framework between described upper system with bottom system, described framework is provided with relatively-movable main robot.
Owing to have employed said structure, interior surrounding layer is entered in vacuum shell be divided into two processes by dress discharge port: shell transport outward with shell in transport.Because covering is strip, in order to keep the steady of transportation, Ke Wai transportation system is a rectangle housing, housing can with row crane by three groups of suspension centre handlings, covering is fixed on the mechanical arm in housing, and housing itself relies on the web joint (UIOS) of TF to position and fix, covering enters after in vacuum shell needs Ke Nei transportation system that covering is transported to final installation site from dress discharge port, and completes the welding of installation action and ooling channel.Interior refuelling system is divided into three parts, the robot of bottom, similar with Divertor structure, therefore can directly directly be entered by lower dress discharge port.Utilize divertor orbital motion, the gear adopting stepping motor to drive provides power, main effect be support refuelling system weight, utilize mechanical arm to weld the ooling channel of bottom; The system on top is similar with the original IVT of ITER, comprises track, rail supported system and robot system, and the main effect of upper system is auxiliary guiding and utilizes mechanical arm to weld the ooling channel at top.Main robot utilizes framework to move up and down, and is responsible for seizing covering on both sides by the arms and covering being fixed on inner layer wall.
Subcritical covering refuelling system of the present utility model, described framework is formed by connecting by six segment frames blocks, and wherein the height of each frame block is 1200mm; Upper sliding shape track offering at circumferentially angle is the opening of 20 °.
Owing to have employed said structure, Xia Liangge robot becomes an entirety by six segment frames anatomical connectivity, common hoop motion, is responsible for covering to be transported to assigned address from dress discharge port.Independent each frame height is 1200mm, can be entered by lower port and utilize main robot to build piecemeal; Its middle orbit reserves the opening at 20 degree of angles, for the turnover of covering.
In sum, owing to have employed technique scheme, the beneficial effects of the utility model are:
1, subcritical covering refuelling system of the present utility model, overcomes ITER little module manifold complicated, and flow resistance is large, and heat exchange efficiency is low, and the reload efficiency of reloading of mode of little module is low, and process of reloading complexity, is difficult to the shortcoming changed to strip energy module;
2, subcritical covering refuelling system of the present utility model, reduces tube fluid resistance, increases the flow of single cladding modular, improves the heat-exchange capacity of the subcritical covering of ITER fission fusion hybrid reactor; Reduce the installation difficulty of cladding modular, be conducive to the maintenance in later stage, safeguard and reload.
Accompanying drawing explanation
The utility model illustrates by example and with reference to the mode of accompanying drawing, wherein:
Fig. 1 and Fig. 2 is the schematic diagram of the vacuum shell being provided with shell induction system in the utility model;
Fig. 3 is the partial schematic diagram of vacuum shell in the utility model;
Fig. 4 is the hermetically-sealed construction filling discharge port in the utility model;
Fig. 5, Fig. 6 and Fig. 7 are the procedure charts that in the utility model, surrounding layer enters shell;
Fig. 8, Fig. 9 and Figure 10 are the procedure charts that in the utility model, inner cladding enters shell;
Figure 11 and Figure 12 is the schematic diagram of transportation system in the utility model mesochite.
Mark in figure: 1-vacuum shell, 2-fills discharge port, 3-mechanical arm, 4-web joint, 5-Ke Wai transportation system, the upper interface of 6-, the attached shielding slab of 7-, 8-shielding slab, 9-bolt and flange face, 10-sealing strip, 11-surrounding layer, 12-inner cladding, 13-divertor track, the upper sliding shape track of 14-, 15-main robot, 16-upper system, 17-bottom system.
Embodiment
All features disclosed in this instructions, or the step in disclosed all methods or process, except mutually exclusive feature and/or step, all can combine by any way.
Arbitrary feature disclosed in this instructions (comprising any accessory claim, summary), unless specifically stated otherwise, all can be replaced by other equivalences or the alternative features with similar object.That is, unless specifically stated otherwise, each feature is an example in a series of equivalence or similar characteristics.
As shown in Figures 1 to 12, subcritical covering refuelling system of the present utility model, vacuum shell 1 is provided with 18 web joints 4, described web joint 4 is formed by connecting by two symmetrical web joint module bolts, it is characterized in that: between two web joint modules of a web joint 4 wherein, have additional TF upper junction plate, described TF upper junction plate is between two TF coils, and the web joint module of described TF upper junction plate and both sides is bolted; Described TF upper junction plate offers the dress discharge port 2 be communicated with inside and outside vacuum shell 1.Wherein said vacuum shell 1 includes inside and outside two-layer, and the downside of described dress discharge port 2 extends to internal layer, and the upside of dress discharge port 2 extends to upper interface 6 place of vacuum shell 1, and flushes with the outer attached shielding slab 7 at former upper interface 6 place; The shielding slab 8 arranged in vacuum shell 1 inside at dress discharge port 2 place matches with vacuum shell 1, and described shielding slab 8 leads to upper interface 6 with the cooling duct of dress discharge port 2 by the sidewall filling discharge port 2.The top of wherein said shielding slab 8 is set to dress discharge port 2 flange face mutually mated respectively, and described shielding slab 8 forms first at dress discharge port 2 place by bolt and sealing ring and seals; The sheet metal seal welding arranged above described shielding slab 8 forms second sealing on dress discharge port 2.Wherein said vacuum shell 1 is provided with carrier in the outer carrier of shell and shell, dress discharge port 2 place in vacuum shell 1 is located at by the outer carrier of described shell, the outer carrier of described shell comprises rectangular housing and can fix the mechanical arm 3 of interior surrounding layer, described housing is connected to dress discharge port 2 place, and described mechanical arm 3 is located in housing; In described shell, carrier comprises and is located at divertor track 13 in vacuum shell 1 and upper sliding shape track 14, on described divertor track 13, coupling has bottom system 17, the motor that described bottom system 17 is arranged is driven through gear and coordinates with divertor track 13 and provide power, on described sliding shape track 14, coupling has upper system 16, described upper system 16 is provided with welding robot, described upper system 16 is connected by framework with between bottom system 17, and described framework is provided with relatively-movable main robot 15.Wherein said framework is formed by connecting by six segment frames blocks, and wherein the height of each frame block is 1200mm; Upper sliding shape track 14 offering at circumferentially angle is the opening of 20 °.
The material-changing method of subcritical covering refuelling system of the present utility model, it comprises, and surrounding layer enters shell process, inner cladding enters shell process and inside transport installation process;
As shown in Figures 5 to 7, wherein wrapping into shell process is outward: surrounding layer 11 rotates to proper angle by a, mechanical arm 3; Surrounding layer 11 contacts to being displaced downwardly to circumferential magnet by b, mechanical arm 3; C, surrounding layer 11 prolonged its bending direction by mechanical arm 3 and be rotated down; D, continue to move down surrounding layer 11 until enter completely;
As shown in Fig. 8 to Figure 10, wherein inner cladding enters shell process and is: inner cladding 12 contacts to being displaced downwardly to circumferential magnet by a, mechanical arm 3; B, by mechanical arm 3 by inner cladding 12 to translation in vacuum shell 1; C, by mechanical arm 3 inner cladding 12 to be moved to downwards and enter completely;
As is illustrated by figs. 11 and 12, wherein inside transport installation process is: inside and outside covering enters after in vacuum shell 1, main robot 15 is built piecemeal and is pressed on the inner layer wall of vacuum shell 1, is completed the welding of interior surrounding layer and ooling channel by welding robot.
To sum up, subcritical covering refuelling system of the present utility model and material-changing method thereof, overcome ITER little module manifold complicated, flow resistance is large, and heat exchange efficiency is low, and the reload efficiency of reloading of mode of little module is low, process of reloading complexity, is difficult to the shortcoming changed to strip energy module; Reduce tube fluid resistance, increase the flow of single cladding modular, improve the heat-exchange capacity of the subcritical covering of ITER fission fusion hybrid reactor; Reduce the installation difficulty of cladding modular, be conducive to the maintenance in later stage, safeguard and reload.
The utility model is not limited to aforesaid embodiment.The utility model expands to any new feature of disclosing in this manual or any combination newly, and the step of the arbitrary new method disclosed or process or any combination newly.
Claims (5)
1. a subcritical covering refuelling system, vacuum shell (1) is provided with 18 web joints (4), described web joint (4) is formed by connecting by two symmetrical web joint module bolts, it is characterized in that: between two web joint modules of a web joint (4) wherein, have additional TF upper junction plate, described TF upper junction plate is between two TF coils, and the web joint module of described TF upper junction plate and both sides is bolted; Described TF upper junction plate offers the dress discharge port (2) be communicated with inside and outside vacuum shell (1).
2. subcritical covering refuelling system as claimed in claim 1, it is characterized in that: described vacuum shell (1) includes inside and outside two-layer, the downside of described dress discharge port (2) extends to internal layer, the upside of dress discharge port (2) extends to upper interface (6) place of vacuum shell (1), and flushes with the outer attached shielding slab (7) at former upper interface (6) place; The shielding slab (8) arranged in vacuum shell (1) inside at dress discharge port (2) place matches with vacuum shell (1), and described shielding slab (8) leads to upper interface (6) with the cooling duct of dress discharge port (2) by the sidewall filling discharge port (2).
3. subcritical covering refuelling system as claimed in claim 2, it is characterized in that: the top of described shielding slab (8) is set to dress discharge port (2) flange face mutually mated respectively, described shielding slab (8) forms first at dress discharge port (2) place by bolt and sealing ring and seals; The sheet metal seal welding that described shielding slab (8) top is arranged forms second sealing in dress discharge port (2) is upper.
4. the subcritical covering refuelling system as described in one of claims 1 to 3, it is characterized in that: described vacuum shell (1) is provided with carrier in the outer carrier of shell and shell, dress discharge port (2) place in vacuum shell (1) is located at by the outer carrier of described shell, the outer carrier of described shell comprises rectangular housing and can fix the mechanical arm (3) of interior surrounding layer, described housing is connected to dress discharge port (2) place, and described mechanical arm (3) is located in housing, in described shell, carrier comprises and is located at divertor track (13) in vacuum shell (1) and upper sliding shape track (14), the upper coupling of described divertor track (13) has bottom system (17), the upper motor arranged in described bottom system (17) is driven through gear and coordinates with divertor track (13) and provide power, the upper coupling of described sliding shape track (14) has upper system (16), (16) are provided with welding robot to described upper system, be connected by framework between described upper system (16) with bottom system (17), described framework is provided with relatively-movable main robot (15).
5. subcritical covering refuelling system as claimed in claim 4, it is characterized in that: described framework is formed by connecting by six segment frames blocks, wherein the height of each frame block is 1200mm; Upper sliding shape track (14) offering at circumferentially angle is the opening of 20 °.
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| CN201420471827.6U CN204087826U (en) | 2014-08-21 | 2014-08-21 | A kind of subcritical covering refuelling system |
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| CN201420471827.6U CN204087826U (en) | 2014-08-21 | 2014-08-21 | A kind of subcritical covering refuelling system |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104134476A (en) * | 2014-08-21 | 2014-11-05 | 中国工程物理研究院核物理与化学研究所 | Subcritical blanket refuelling system and refuelling method thereof |
| CN105976873A (en) * | 2016-03-02 | 2016-09-28 | 中国科学院等离子体物理研究所 | Internal part cooling power generation system for future tokamak fusion reactor |
| CN109817353A (en) * | 2019-02-01 | 2019-05-28 | 中国工程物理研究院核物理与化学研究所 | A kind of Fusion-fission covering refuelling system and its material-changing method |
| CN110619963A (en) * | 2019-10-14 | 2019-12-27 | 中国科学院合肥物质科学研究院 | Tokamak fusion device internal part arrangement structure convenient for remote operation and maintenance |
-
2014
- 2014-08-21 CN CN201420471827.6U patent/CN204087826U/en active Active
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104134476A (en) * | 2014-08-21 | 2014-11-05 | 中国工程物理研究院核物理与化学研究所 | Subcritical blanket refuelling system and refuelling method thereof |
| CN105976873A (en) * | 2016-03-02 | 2016-09-28 | 中国科学院等离子体物理研究所 | Internal part cooling power generation system for future tokamak fusion reactor |
| CN109817353A (en) * | 2019-02-01 | 2019-05-28 | 中国工程物理研究院核物理与化学研究所 | A kind of Fusion-fission covering refuelling system and its material-changing method |
| CN110619963A (en) * | 2019-10-14 | 2019-12-27 | 中国科学院合肥物质科学研究院 | Tokamak fusion device internal part arrangement structure convenient for remote operation and maintenance |
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