CN204303357U - A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction - Google Patents
A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction Download PDFInfo
- Publication number
- CN204303357U CN204303357U CN201420816079.0U CN201420816079U CN204303357U CN 204303357 U CN204303357 U CN 204303357U CN 201420816079 U CN201420816079 U CN 201420816079U CN 204303357 U CN204303357 U CN 204303357U
- Authority
- CN
- China
- Prior art keywords
- tritium
- submodule
- plate
- shaped
- intermediate plate
- 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.)
- Active
Links
Classifications
-
- 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
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model belongs to a kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction.It comprises submodule, after each submodule includes U-shaped first wall, upper and lower two cover plates and submodule, plate system is as outer boundary, inside is provided with intermediate plate, intermediate plate both sides are provided with two groups of double-deck U-shaped helium gas cooling plates, submodule inside is divided into neutron multiplication district and tritium breeding blanket by double-deck U-shaped helium gas cooling plate and intermediate plate, after submodule, plate system is provided with helium cooling duct that helium gas cooling plate U-shaped with bilayer, cover plate and intermediate plate communicate and communicate with tritium breeding blanket and neutron multiplication district carry tritium pipeline.Its advantage is, the modular construction that have employed; In submodule, have employed double-deck U-shaped coldplate, be formed with the neutron multiplication district and tritium breeding blanket structural arrangement that are beneficial to tritium propagation; Have employed bypass, be conducive to the control of coolant flow, thus can ensure that it realizes tritium propagation and high efficiency energy extraction test the prerequisite of the stability and safety operation of window at ITER under.
Description
Technical field
The invention belongs to a kind of covering proving installation of fusion energy resource, be specifically related to a kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction.
Background technology
In controlled thermonuclear fusion research field, tritium propagation and high efficiency energy extractive technique are the gordian techniquies realizing Magnetic-confinement thermonuclear fusion reaction generating.Experiment cladding modular will carry out the functional test of tritium propagation and Energy extraction on International Thermal-Nuclear Experimental Reactor (ITER) as vitals.ITER device is very strict for the requirement of experiment cladding modular, for realizing the gordian technique of above-mentioned two nuclear fusion reactions, a kind of novel modular design, the direct flux of plasma of submodule, functional material are proposed by two groups of double-deck U-shaped plate lattice, independently cooling systems and the experiment cladding modular structural design putting forward tritium system.
In ITER device, experiment cladding modular is by the impact in the face of high-energy high flux neutron and high heat load, under this extreme operating condition, how not only ensure that experiment cladding modular does not affect the safe operation of ITER device but also can realize tritium propagation and high efficiency energy extracts two big experiment targets, there is very great challenge.
Summary of the invention
The object of this invention is to provide one and can ensure that tritium is controlled oneself and high efficiency energy extracts, thus the experiment covering proving installation for producing tritium and heat extraction of breeding for tritium of guaranteeing that magnetic confinement fusion can realize and Energy extraction.
The present invention realizes like this, a kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction, it comprises submodule, each submodule includes U-shaped first wall, after upper and lower two cover plates and submodule, plate system is as outer boundary, inside is provided with intermediate plate, intermediate plate both sides are provided with two groups of double-deck U-shaped helium gas cooling plates, submodule inside is divided into neutron multiplication district and tritium breeding blanket by double-deck U-shaped helium gas cooling plate and intermediate plate, plate system is provided with bilayer U-shaped helium gas cooling plate after submodule, the helium cooling duct that cover plate and intermediate plate communicate and communicate with tritium breeding blanket and neutron multiplication district carry tritium pipeline.
It comprises large rear plate, submodule is welded on large rear plate, the pipeline one_to_one corresponding of its inside pipeline and submodule, the helium cooling duct in outside and carry tritium pipeline and be all respectively equipped with two, one as entrance, another is as outlet, and bypass duct is for regulating the difference in flow of helium cooling duct gateway.
Advantage of the present invention is, the modular construction that have employed; In submodule, have employed double-deck U-shaped coldplate, be formed with the neutron multiplication district and tritium breeding blanket structural arrangement that are beneficial to tritium propagation; Have employed bypass, be conducive to the control of coolant flow, thus can ensure that it realizes tritium propagation and high efficiency energy extraction test the prerequisite of the stability and safety operation of window at ITER under.
Accompanying drawing explanation
Fig. 1 is a kind of schematic diagram of Novel experimental covering proving installation submodule for tritium propagation and heat extraction provided by the present invention;
Fig. 2 is a kind of inner structure cut-open view of Novel experimental covering proving installation submodule for tritium propagation and heat extraction provided by the present invention;
Fig. 3 is large plate and the submodule wiring layout afterwards of a kind of Novel experimental covering proving installation for tritium propagation and heat extraction provided by the present invention;
Fig. 4 is a kind of overall diagram of Novel experimental covering proving installation for tritium propagation and heat extraction provided by the present invention.
In figure: 1U type first wall, 2 submodules, 3 large rear plates, 4 helium cooling ducts, 5 bypass ducts, 6 carry tritium pipeline, 7 joint pins, 8 cover plates, plate system after 9 submodules, 10 intermediate plates, 11 tritium breeding blankets, 12 neutron multiplication districts, 13 double-deck U-shaped coldplates.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
As Fig. 1, shown in 2, a kind of Novel experimental covering proving installation for tritium propagation and heat extraction comprises submodule 2, each submodule 2 includes U-shaped first wall 1, after upper and lower two cover plates 8 and submodule, plate system 9 is as outer boundary, there is intermediate plate 10 inside, intermediate plate 10 both sides are provided with two groups of double-deck U-shaped helium gas cooling plates 13, the neutron multiplication district 12 that submodule inside is divided into favourable tritium to breed by double-deck U-shaped helium gas cooling plate 13 and intermediate plate 10 and tritium breeding blanket 11, plate system 9 is provided with bilayer U-shaped helium gas cooling plate 13 after submodule, the helium cooling duct 4 that cover plate 8 and intermediate plate 10 communicate and communicate with tritium breeding blanket 11 and neutron multiplication district 12 carry tritium pipeline 6.
Described tritium breeding blanket 11 is the fill areas of the tritium multiplication agent piled up in pellet form, the impact from pressure, temperature, thermograde and thermal shock in ITER operational process can be born, even if simultaneously bead reaches most high burnup at ITER run duration, also can not there is too much breakage and affect the flowing putting forward tritium gas, can keep with structured material, carry in tritium gas environment and keep good compatibility.Described neutron multiplication district 12 is the regions of filling using beryllium bead as neutron multiplication agent, has good neutron multiplication effect and thermodynamic property.
As shown in Figure 3 and Figure 4 for tritium propagation and the experiment covering test module overall schematic of heat extraction, have 4 submodules in the present embodiment and form whole test module, submodule 2 is arranged on greatly afterwards on plate 3.The first wall 1 in submodule 2 is the double panel structure that 30mm is thick, becomes U-shaped, includes cooling duct.First wall 1 can bear high heat load and the Neutron wall loading of ITER experimental provision.Flow through with high speed helium in the process of the first wall 1 and realize Energy extraction.
Described rear plate 3 be provided with helium cooling duct 4 and carry tritium pipeline 6, respectively with the helium cooling duct 4 on each submodule 2 with carry tritium pipeline 6 and communicate.Helium cooling duct 4 after large on plate 3 and carry tritium pipeline 6 and be respectively equipped with two, one as entrance, another is as outlet.Corresponding with the entrance and exit carrying tritium pipeline 4 with the helium cooling duct 3 on submodule 2 during installation.In addition, after large, plate 3 is also equipped with shunt valve 5 for controlling the gateway difference in flow of helium cooling tube 4, joint pin 7 is for the connection of described tentative module and its back part.
During work, the entrance of the helium cooling duct 4 on large rear plate 3 fills 8MPa/300 DEG C, the helium of 1.3kg/s is as cooling medium, the first wall 1 is given after being shunted by large rear plate 3, its rear section is flowed out through bypass duct 5, all the other enter each submodule 2, flow through plate system 9 after the submodule of submodule 2 inside, cover plate 8, intermediate plate 10 and helium gas cooling plate 13, and then flow out through the outlet of helium cooling duct 4, be pooled to the outlet of the helium cooling duct 4 of large rear plate 3 again, thus form whole cooling circuit, by controlling submodule region coolant flow, to reach the object controlling tritium propagation Qiu Chuan district temperature.
The entrance carrying tritium pipeline 6 on large rear plate 3 fills the helium of 0.12Mpa, each submodule 2 is given after being shunted by large rear plate 3, flow through neutron multiplication district 12 and the tritium breeding blanket 11 of submodule 2 inside, extract tritium during the course, by proposing the outlet of tritium pipeline 6, be pooled to the outlet carrying tritium pipeline 6 of large rear plate 3, thus realize tritium in the release of optimum temperature region, infiltration and extraction.
Claims (2)
1. one kind for tritium propagation and the Novel experimental covering proving installation of heat extraction, it is characterized in that: it comprises submodule (2), each submodule (2) includes U-shaped first wall (1), after upper and lower two cover plates (8) and submodule, plate system (9) is as outer boundary, inside is provided with intermediate plate (10), intermediate plate (10) both sides are provided with two groups of double-deck U-shaped helium gas cooling plates (13), submodule inside is divided into neutron multiplication district (12) and tritium breeding blanket (11) with intermediate plate (10) by double-deck U-shaped helium gas cooling plate (13), plate system (9) is provided with bilayer U-shaped helium gas cooling plate (13) after submodule, the helium cooling duct (4) that cover plate (8) and intermediate plate (10) communicate and communicate with tritium breeding blanket (11) and neutron multiplication district (12) carry tritium pipeline (6).
2. a kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction as claimed in claim 1, it is characterized in that: it comprises large rear plate (3), its helium cooling duct (4) and carry tritium pipeline (6) and be all respectively equipped with two, one as entrance, another is as outlet, and bypass duct (5) regulates the difference in flow of helium cooling duct (4) gateway.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420816079.0U CN204303357U (en) | 2014-12-19 | 2014-12-19 | A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420816079.0U CN204303357U (en) | 2014-12-19 | 2014-12-19 | A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204303357U true CN204303357U (en) | 2015-04-29 |
Family
ID=53108879
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201420816079.0U Active CN204303357U (en) | 2014-12-19 | 2014-12-19 | A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN204303357U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105761762A (en) * | 2014-12-19 | 2016-07-13 | 核工业西南物理研究院 | Novel test blanket testing device for tritium breeding and heat rejection |
| CN105976874A (en) * | 2016-02-26 | 2016-09-28 | 中国科学院等离子体物理研究所 | Partition tritium purging system suitable for fusion reactor solid cladding |
-
2014
- 2014-12-19 CN CN201420816079.0U patent/CN204303357U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105761762A (en) * | 2014-12-19 | 2016-07-13 | 核工业西南物理研究院 | Novel test blanket testing device for tritium breeding and heat rejection |
| CN105976874A (en) * | 2016-02-26 | 2016-09-28 | 中国科学院等离子体物理研究所 | Partition tritium purging system suitable for fusion reactor solid cladding |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Del Nevo et al. | WCLL breeding blanket design and integration for DEMO 2015: status and perspectives | |
| CN201877134U (en) | TBW for tritium breeding and energy extraction | |
| Hernández et al. | Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program | |
| Merola et al. | Overview and status of ITER internal components | |
| CN105761762A (en) | Novel test blanket testing device for tritium breeding and heat rejection | |
| Aiello et al. | Development of the helium cooled lithium lead blanket for DEMO | |
| Puma et al. | Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant | |
| Ni et al. | Structural design and preliminary analysis of liquid lead–lithium blanket for China Fusion Engineering Test Reactor | |
| Wu et al. | Design optimization and analysis of CN HCCB TBM-set | |
| Zhou et al. | Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor | |
| CN104021819A (en) | Design of cooling and tritium extracting loop for helium cooling solid state tritium multiplication covering layer multiplication unit | |
| Lian et al. | Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket | |
| Liu et al. | Thermal–mechanical analysis of the first wall for CFETR helium cooled solid breeder blanket | |
| CN204303357U (en) | A kind of for tritium propagation and the Novel experimental covering proving installation of heat extraction | |
| Chaudhuri et al. | Overview of design and thermal–hydraulic analysis of Indian solid breeder blanket concept | |
| Kim et al. | Status of ITER TBM port plug conceptual design and analyses | |
| Chaudhuri et al. | Thermal-hydraulics of LLCB TBM under different ITER operational conditions | |
| Chaudhuri et al. | Current status of design and engineering analysis of Indian LLCB TBM | |
| Cho et al. | Current status of design and analysis of Korean helium-cooled solid breeder test blanket module | |
| Aubert et al. | Status on DEMO Helium Cooled Lithium Lead breeding blanket thermo-mechanical analyses | |
| Wang et al. | Preliminary accident analyses of in-vessel LOCA and In-box LOCA for China helium-cooled ceramic breeder test blanket system | |
| Aubert et al. | DEMO Breeding Blanket Helium Cooled First Wall design investigation to cope high heat loads | |
| Nomoto et al. | Structural concept of Japanese solid breeder test blanket modules for ITER | |
| Wang et al. | Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system | |
| Tillack et al. | ARIES-ACT1 power core engineering |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |