CN106898383A - A kind of product tritium module of Fusion-fission cladding systems - Google Patents
A kind of product tritium module of Fusion-fission cladding systems Download PDFInfo
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- CN106898383A CN106898383A CN201710206820.XA CN201710206820A CN106898383A CN 106898383 A CN106898383 A CN 106898383A CN 201710206820 A CN201710206820 A CN 201710206820A CN 106898383 A CN106898383 A CN 106898383A
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- Prior art keywords
- module
- tritium
- fission
- fusion
- tritium module
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/01—Hybrid fission-fusion nuclear reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
-
- 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
Abstract
The invention discloses a kind of product tritium module of Fusion-fission cladding systems, including:The product tritium module is U-shaped zirconium cladding and spherical Li including section4SiO4Proliferating agent, it is U-shaped dividing plate that some sections are provided with the zirconium cladding, and water stream channel and helium passages, water stream channel and helium passages interval setting are formed between dividing plate, and Li is filled with helium passages4SiO4Proliferating agent.Technical purpose of the invention is to provide a kind of product tritium module that can improve the Fusion-fission cladding systems that neutron is utilized.
Description
Technical field
The present invention relates to nuclear fusion fission reactor technical field, more particularly to a kind of product tritium of Fusion-fission cladding systems
Module.
Background technology
The energy is the material base of modern economy social development, is also the important restriction factor of socio-economic development, the energy
Concerning economic security and national security, influence of the energy resource consumption to ecological environment becomes increasingly conspicuous safety.China is used as the first in the world
Populous nation and the developing country of maximum, have been world's second largest production of energy state and country of consumption.In face of the energy of growing tension
Source situation, China advocates energy-saving energetically, and improves constantly production and the utilization ratio of the existing energy.The current energy of China
Based on coal, not only the supply capacity of coal faces enormous pressure for consumption, coal largely produce and use present in resource return
Adopt low rate, flue dust, dust, NOx and CO2 discharge capacitys all will cause enormous pressure to ecological environment, it is seen then that realize building
The target of " low-carbon (LC) " society, China needs to improve energy resource structure energetically.China《Nuclear power Long-and Medium-term Development is planned(2005 -2020
Year)》Point out that nuclear energy is a kind of safe and clean, reliable energy, meanwhile, Development Stratagem Of Nuclear Power is changed into by " optimum development "
" actively development ".The large scale deployment of nuclear energy, need to coordinate to resolve the level of resources utilization and the problems such as spentnuclear fuel is post-processed.Heat
The uranium resource utilization ratio of neutron pile only has 1%, medium-term and long-term to continue extensive development and limited by uranium resource utilization ratio is low.
Uranium resource utilization ratio can be brought up to 60% by fast neutron reactor, and current technology develops also comparative maturity, be expected to turn into a new generation
Main force's nuclear power system, but reactor core filled at the beginning of fast reactor need a large amount of enriched uranium and plutonium, fuel post processing needs isotopic separation and uranium plutonium
Separate, and there is restricting relation between fuel breeding speed and security, thus the fuel multiplication cycle is very long, in the middle of this century
The even longer time is all difficult to large scale deployment.Within predictable one period, the commercialization energy source use of pure fusion is also
Cannot realize, it is main by material radiation-resistant property, realize commercial electricity production needed for Q high(Fusion releases energy and realizes fusion
The ratio between heat energy of required offer)It is worth difficult limitation, is also limited by tritium resource on long terms.Traditional concept it is mixed
Conjunction heap is mainly carries out Nuclear fuel breeding and nuke rubbish transmuting, and they mostly have system complex, need fuel post processing, economy
The features such as scientific and technical problem that is poor and being limited to pure fusion reactor core, thus traditional function positioning hybrid reactor be difficult to obtain compared with
Great development.
The content of the invention
For above-mentioned problem, technical purpose of the invention is to provide a kind of product tritium of Fusion-fission cladding systems
Module.
The present invention is achieved through the following technical solutions:
The product tritium module of Fusion-fission cladding systems of the invention, including:The product tritium module is U-shaped zirconium cladding including section
And spherical Li4SiO4Proliferating agent, it is U-shaped dividing plate that some sections are provided with the zirconium cladding, and water stream channel is formed between dividing plate
And helium passages, water stream channel and helium passages interval setting, Li is filled with helium passages4SiO4Proliferating agent.
The product tritium module of Fusion-fission cladding systems of the invention, producing tritium module includes passing through water slowing down cooling tube and helium
The top managed and be sequentially connected is produced tritium module, middle part and produces tritium module and bottom product tritium module, and tritium module and bottom are produced in the top
It is trapezoidal to produce tritium module, and it is rectangle that tritium module is produced at middle part.
The product tritium module of Fusion-fission cladding systems of the invention, the water slowing down cooling tube includes being connected with water stream channel
Water inlet pipe and outlet pipe, helium tube includes the air inlet pipe that is connected with helium passages and blast pipe.
The beneficial effects of the invention are as follows:
The mutual only of the water slowing down cooling tube and tritium multiplication agent bead area produced in tritium module is ensure that by the product tritium module being provided with
It is vertical, Li during steady-state operation4SiO4Helium carrier band tritium, Li are passed through in ball bed gap again4SiO4Bead fill area is also taken into account and constitutes helium
Airborne tritium runner, maximizes the utilization of Fusion Neutron, and reduces the keff needed for realizing expected energy gain and tritium breeding ratio,
Improve and produce tritium efficiency, covering works under depth subcritical state, it is ensured that maintenance reaction heap is subcritical under any circumstance.
Brief description of the drawings
Fig. 1 is the single-lobe cladding structure figure of the cladding systems of fusion-fission reaction heap;
Fig. 2 is the single-lobe covering supporting construction figure of the cladding systems of fusion-fission reaction heap;
Fig. 3 is the single-lobe covering fuel module structure chart of the cladding systems of fusion-fission reaction heap;
Fig. 4 is coolant pressure tubular construction figure in the fuel module of middle part;
Fig. 5 is coolant pressure tubular construction figure in lower fuel module;
Fig. 6 is local structural graph of the coolant pressure pipe in fuel module;
Fig. 7 is the structure chart for producing tritium module;
Fig. 8 is the partial enlarged drawing of A in Fig. 5;
Fig. 9 is that the single-lobe covering of the cladding systems of fusion-fission reaction heap produces tritium function structure chart.
Marked in figure:1 for produce tritium module, 101 be top produce tritium module, 102 be middle part produce tritium module, 103 be that is produced from bottom
Tritium module, 104 be dividing plate, 105 be helium passages, 106 be zirconium cladding, 107 be Li4SiO4Proliferating agent, 108 be water stream channel,
109 is water slowing down cooling tube, 110 is water inlet pipe, 111 is outlet pipe, 112 is helium tube, 113 is air inlet pipe, 114 is to be vented
Pipe, 2 be fuel module, 201 be coolant pressure pipe, 3 be engineering path, 4 be supporting arrangement, 401 be inner groovy, 402 for horizontal stroke
To muscles and bones, 403 be pole to vertical bone, 5 be positioning and guiding dividing plate, 6 be water injection hole, 7 be lower fuel module, 8 be middle part fuel mould
Block, 9 are top fuel module.
Specific embodiment
The present invention is described in detail below in conjunction with the accompanying drawings.
As shown in Figure 1, Figure 2, the cladding systems of the fusion-fission reaction heap shown in Fig. 3, Fig. 4, Fig. 5, Fig. 6, Fig. 7, Fig. 8 and Fig. 9,
Including:18 valve cladding modulars, the cladding modular splicing is wrapped in outside fusion target room and the cladding systems of 360 ° of formation, per valve bag
Layer module includes the fuel module 2 and supporting arrangement 4 of the product tritium module 1, some connections of some connections, the top of the cladding systems
Portion is provided with the opening for installing fusion load, and bottom is provided with the opening for installing tritium recovery system more than reactor core, the supporting
Device 4 has the inner fovea part 401 towards fusion target chamber center, and the cladding systems are hexagon, institute along the cross sectional shape of the longitudinal axis
State hexagon symmetrical along the longitudinal axis, the inner surface of the inner fovea part 401 is coated with product tritium module 1 and fuel module 2, the product tritium module
1 sees located at the outer layer of fuel module 2, produces tritium module 1 and fuel module 2 is separately fabricated and install.
Engineering path 3 is additionally provided between the product tritium module 1 and fuel module 2, engineering path 3 is in severe accident conditions
Under, containment is built-in with safety radiator, by gravity it is passive to water filling in engineering path, water is from the bottom of engineering path 3
Into, and from the flowing of the bottom up of engineering path 3, by natural circulation cooling fuel module internal face, realize heat in heap
Derive, when heat is discharged, engineering path inside supporting frame can bear shock loading during major accident, and engineering is logical
Road 3 is not usually required to maintenance on a large scale, and reliability cyclic check can be carried out during cold-refueling.Engineering path water filling system
System, outside cladding systems, is connected by pipeline with engineering path, belongs to independent security system, in accident, with fuel
Used as control signal, temperature reaches setting valve i.e. activation system to temperature, and containment inner water-tank is noted by potential difference to engineering path
Water, floods subcritical energy covering.Steam is produced to rely on Passive containment cooling system(Containment top heat exchanger)By heat
Amount is delivered to the external water storage tank of containment, and condensed water is back to containment inner water-tank and melt pit after being collected through containment return flume
In, realize closed cycle.Engineering path 3 can improve the confining force in zirconium tank wall after major accident.Under major accident operating mode, work
Cheng Tongdao 3 makes the heat of fuel module be discharged by the boiling water near fuel region zirconium tank wall, and fuel region can be controlled to melt
Process, keeps the integrality of subcritical energy covering.Full of water and fuel region heat by water and produced in the engineering path 3
Steam by zirconium tank wall derive during, engineering path can bear the impact pressure difference of step.
The supporting arrangement 4 includes horizontal muscles and bones 402 and pole to vertical bone 403, and horizontal muscles and bones 402 connect pole to vertical bone 403
Connect fixation.Above-mentioned, covering external force is born and transmitted in pole, as cladding systems stand under load main body, to vertical bone 403, and horizontal muscles and bones 402 are used
Intensity, rigidity and the stability of indulging bone are supported really in improving.Supporting arrangement 4 can be set to vertical bone 403 from 4 poles with some levels
The horizontal muscles and bones 402 put weld together, and supporting arrangement 4 is provided with the support structure of triangle near reactor core upper lateral part and bottom
Part, the supporting member of triangle is supported by way of oblique pull, so as to form inner fovea part 401, indent on supporting arrangement 4
Portion 401 is used to install product tritium module 1 and fuel module 2 and engineering path 3, and this supporting arrangement 4 can reduce neutronics performance
Loss.
The fuel module 2 includes the top fuel module 9, middle part fuel module 8 and the lower fuel module that are sequentially connected
7, top fuel module 9 is trapezium structure with lower fuel module 7, and middle part fuel module 8 is rectangular configuration, top fuel module
9 are symmetrical arranged with lower fuel module 7, and the cooling agent in the coolant pressure pipe 201 of fuel module therein 2 flows from bottom to top
It is dynamic.The fuel module 2 is included in shell 202, the fission fuel 203 in shell and the embedded fission fuel of zirconium material
Coolant pressure pipe 201.2~6 layers of coolant pressure pipe are embedded with the top fuel module 9 and lower fuel module 7
201, coolant pressure pipe 201 can be 3 layers, and every layer of coolant pressure pipe inflection shape is arranged in top fuel module 9 with
In portion's fuel module 7, the coolant pressure pipe 201 in the middle part fuel module 8 is longitudinally arranged, the top fuel module 9,
Coolant pressure pipe 201 in middle part fuel module 8 and lower fuel module 7 is sequentially communicated.Fuel module 2 is that composition is subcritical
The basic structural unit of energy covering active region, is achieved in neutron multiplication and releases nuclear fission energy, is the heat release of energy covering
Element, can be very good to ensure circuit pressure boundary integrity, fuel module using embedded pressure tubular type cooling agent pipeline configuration
In embed coolant pressure pipeline be designed to connect communicating structure, cooling agent can be by these embedded coolant pressure pipes
201 heats for taking away active region;In order to prevent fission products from being leaked out from fuel module, so fuel module is designed with
The zirconium cladding of case casket sealing structure, so as to realize the shielding to fuel fission product.
The inner surface of the inner fovea part 401 is longitudinally provided with some positioning and guiding dividing plates 5 for supporting fuel module, described every
Block positioning and guiding dividing plate 5 is installed along the latitude direction of cladding systems, and the positioning and guiding dividing plate 5 is provided with and leads to for connecting engineering
The water injection hole 6 in road.
The product tritium module 1 is U-shaped zirconium cladding 106 and spherical Li including section4SiO4Proliferating agent 107, the zirconium bag
It is U-shaped dividing plate 109 to be provided with some sections in shell 106, and water stream channel 108 and helium passages 105, water are formed between dividing plate 109
Circulation road 108 and the interval setting of helium passages 105, are filled with Li in helium passages 1054SiO4Proliferating agent 107, water stream channel 108
And the side of helium passages 105 is provided with import, opposite side is provided with outlet.
The tritium module 1 of producing includes that tritium mould is produced on the top being sequentially connected by water slowing down cooling tube 109 and helium tube 112
Block 101, middle part produces tritium module 102 and tritium module 103 is produced in bottom, and the top product tritium module 101 is produced tritium module 103 and is with bottom
Trapezoidal, it is rectangle that tritium module 102 is produced at middle part, produces the reclaimed water slowing down cooling tube 109 of tritium module 1 and is designed to a kind of " u "-shaped structure, with suitable
Answer the structure of zirconium cladding 106.The water slowing down cooling tube 109 includes the water inlet pipe 110 and outlet pipe that are connected with water stream channel 108
111, helium tube 112 includes the air inlet pipe 113 and the blast pipe 114 that are connected with helium passages 105.
It is described that produce tritium module 1 to use temperature be the light-water of 4Mpa for 150 DEG C, pressure as moderator, the H in runner2O energy
Enough allow in fuel assembly have more than needed neutron enter produce tritium module 1 after reacted with Li-6 again by further slowing down and improve tritium rate of producing,
And the part nuclear heat in tritium breeding blanket is taken away in time to ensure most preferably to release tritium temperature, water stream channel 108 is alternate with helium passages 105
Arrangement, the Li filled with bead shape in helium passages 1054SiO4Proliferating agent, so as to ensure that the coolant flow produced in tritium module
Road and the mutual independence in tritium multiplication agent bead area;Li during steady-state operation4SiO4Proliferating agent ball bed is passed through helium carrier band again in gap
Tritium, so Li4SiO4Proliferating agent bead fill area is also taken into account and constitutes helium load tritium runner such that it is able to improves and produces tritium rate.
The fuel module 2 is towards scribbling low activation ferrite/martensite RAFM steel conducts on the first wall of plasma
Coating, the thickness of the coating is 8~15mm, and the thickness of the first wall can be 12mm, and the first wall can have very strong anti-spoke
According to lesion capability.
Therefore, the cladding systems of the fusion-fission reaction heap and the cladding systems with the fusion-fission reaction heap can be carried
The height fission level of resources utilization, makes full use of depleted uranium and thorium;Only drive away part fission product without carrying out the letter of isotopic separation
Change post-processing approach, can realize that fuel secular equilibrium is circulated;Fission nuclear energy nuke rubbish can be burned, assists fission nuclear energy to realize closure
Circulation;Covering maximizes the utilization of Fusion Neutron close to realizing surrounding fusionplasma completely, and reduces the expected energy of realization
Keff needed for flow gain and tritium breeding ratio, covering works under depth subcritical state, it is ensured that remain anti-under any circumstance
Answer heap subcritical, safer, energy mix heap is considered as alloy-type fuel, and such as natural uranium, depleted uranium, thermal reactor is unloaded
The spentnuclear fuel for going out, front end is not related to uranium enrichment, and rear end is then conducive to simplifying the post processing of discharging, at present the aftertreatment technology of design
The expeling of harmful fission gas and fission fragment is pertained only to without regard to isotopic separation, is extracted in the absence of by unnecessary plutonium
Possibility, thus also just in the absence of nuclear proliferation risk.
Embodiments of the invention are the foregoing is only, the scope of the claims of the invention is not thereby limited, it is every to utilize this hair
Equivalent structure or equivalent flow conversion that bright specification and accompanying drawing content are made, or directly or indirectly it is used in other related skills
Art field, is included within the scope of the present invention.
Claims (5)
1. the product tritium module of a kind of Fusion-fission cladding systems, it is characterised in that including:The product tritium module(1)Including section
It is U-shaped zirconium cladding(106)And spherical Li4SiO4Proliferating agent(107), the zirconium cladding(106)Some sections are inside provided with for U
The dividing plate of type(109), dividing plate(109)Between form water stream channel(108)And helium passages(105), water stream channel(108)With helium
Gas passage(105)Interval setting, helium passages(105)It is interior filled with Li4SiO4Proliferating agent(107).
2. the product tritium module of Fusion-fission cladding systems according to claim 1, it is characterised in that produce tritium module(1)Bag
Include by water slowing down cooling tube(109)And helium tube(112)And tritium module is produced on the top being sequentially connected(101), middle part produce tritium mould
Block(102)Tritium module is produced with bottom(103), tritium module is produced on the top(101)Tritium module is produced with bottom(103)For trapezoidal, in
Produce tritium module in portion(102)It is rectangle.
3. the product tritium module of Fusion-fission cladding systems according to claim 2, it is characterised in that the water slowing down cooling
Pipe(109)Including with water stream channel(108)The water inlet pipe of connection(110)And outlet pipe(111), helium tube(112)Including with helium
Gas passage(105)The air inlet pipe of connection(113)And blast pipe(114).
4. the product tritium module of Fusion-fission cladding systems according to claim 2, it is characterised in that produce tritium mould in the middle part
Block(102)Son product tritium module including multiple rectangles and interconnection.
5. the product tritium module of Fusion-fission cladding systems according to claim 2, it is characterised in that produce tritium mould in the top
Block(101)And tritium module is produced in bottom(103)Tritium module is produced including trapezoidal and interconnection the son of multiple.
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115255594A (en) * | 2022-08-16 | 2022-11-01 | 中国科学院合肥物质科学研究院 | Tool and welding method for electron beam sectional welding of first wall of water-cooled ceramic cladding |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103578574A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core tritium-production blanket |
CN103886921A (en) * | 2014-03-13 | 2014-06-25 | 清华大学 | Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof |
CN104637548A (en) * | 2015-02-16 | 2015-05-20 | 中国科学院合肥物质科学研究院 | Novel cladding fuel management method for fusion-fission hybrid reactor |
US9068562B1 (en) * | 2012-10-05 | 2015-06-30 | The Boeing Company | Laser-powered propulsion system |
US20170025188A1 (en) * | 2008-06-13 | 2017-01-26 | Arcata Systems | Single-pass, heavy ion fusion, systems and method for fusion power production and other applications of a large-scale neutron source |
CN206833930U (en) * | 2017-03-31 | 2018-01-02 | 中国工程物理研究院核物理与化学研究所 | A kind of production tritium module of Fusion-fission cladding systems |
-
2017
- 2017-03-31 CN CN201710206820.XA patent/CN106898383A/en active Pending
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20170025188A1 (en) * | 2008-06-13 | 2017-01-26 | Arcata Systems | Single-pass, heavy ion fusion, systems and method for fusion power production and other applications of a large-scale neutron source |
US9068562B1 (en) * | 2012-10-05 | 2015-06-30 | The Boeing Company | Laser-powered propulsion system |
CN103578574A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy reactor core tritium-production blanket |
CN103886921A (en) * | 2014-03-13 | 2014-06-25 | 清华大学 | Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof |
CN104637548A (en) * | 2015-02-16 | 2015-05-20 | 中国科学院合肥物质科学研究院 | Novel cladding fuel management method for fusion-fission hybrid reactor |
CN206833930U (en) * | 2017-03-31 | 2018-01-02 | 中国工程物理研究院核物理与化学研究所 | A kind of production tritium module of Fusion-fission cladding systems |
Non-Patent Citations (1)
Title |
---|
曾和荣等: "ITER驱动次临界包层总体结构概念设计", 《强激光与粒子束》 * |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115255594A (en) * | 2022-08-16 | 2022-11-01 | 中国科学院合肥物质科学研究院 | Tool and welding method for electron beam sectional welding of first wall of water-cooled ceramic cladding |
CN115255594B (en) * | 2022-08-16 | 2023-09-08 | 中国科学院合肥物质科学研究院 | Tool and welding method for electron beam sectional welding of water-cooled ceramic cladding first wall |
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Application publication date: 20170627 |