CN106816181A - A kind of cladding systems of fusion-fission reaction heap - Google Patents

A kind of cladding systems of fusion-fission reaction heap Download PDF

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Publication number
CN106816181A
CN106816181A CN201710207659.8A CN201710207659A CN106816181A CN 106816181 A CN106816181 A CN 106816181A CN 201710207659 A CN201710207659 A CN 201710207659A CN 106816181 A CN106816181 A CN 106816181A
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module
cladding
fusion
fuel module
tritium
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CN106816181B (en
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刘志勇
黄洪文
曾和荣
郭海兵
马纪敏
王少华
丁文杰
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Institute of Nuclear Physics and Chemistry China Academy of Engineering Physics
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Institute of Nuclear Physics and Chemistry China Academy of Engineering Physics
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/01Hybrid fission-fusion nuclear reactors
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/11Details
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/11Details
    • G21B1/13First wall; Blanket; Divertor
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses a kind of cladding systems of fusion-fission reaction heap, including:Some valve cladding modulars, the cladding modular splicing is wrapped in outside fusion target room and the cladding systems of 360 ° of formation, it is provided with the top of the cladding systems and changes target drone structure installing port, bottom is provided with tritium recovery port more than reactor core, include some connections per valve cladding modular produces tritium module, the fuel module and supporting arrangement of some connections, the supporting arrangement has the inner fovea part towards fusion target chamber center, the inner fovea part inner surface is coated with product tritium module and fuel module, outer layer of the product tritium module located at fuel module.Technical purpose of the invention is a kind of cladding systems of the fusion-fission reaction heap for providing modular construction.

Description

A kind of cladding systems of fusion-fission reaction heap
Technical field
The present invention relates to nuclear fusion fission reactor technical field, more particularly to a kind of covering system of fusion-fission reaction heap System.
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 that to provide a kind of Fusion-fission of modular construction anti- Answering the cladding systems of heap, this cladding systems can utilize to the uranium resource of low concentration so that U238 occurs to split on a large scale Become reaction to amplify energy, the energy output system of subcritical fission covering sets out the heat energy that subcritical fission covering is produced, Avoid the treatment to nuke rubbish.
The present invention is achieved through the following technical solutions:
The cladding systems of fusion-fission reaction heap of the invention, including:Some valve cladding modulars, the cladding modular splicing parcel 360 ° of cladding systems are formed outside fusion target room, is provided with the top of the cladding systems and is changed target drone structure installing port, bottom sets There is tritium recovery port more than reactor core, some connections are included per valve cladding modular produces tritium module, the fuel module of some connections and supporting Device, the supporting arrangement has the inner fovea part towards fusion target chamber center, and the inner fovea part inner surface is coated with product tritium module And fuel module, outer layer of the product tritium module located at fuel module.
The cladding systems of fusion-fission reaction heap of the invention, engineering is additionally provided between the product tritium module and fuel module Passage.
The cladding systems of fusion-fission reaction heap of the invention, the cladding modular is 18 valves, and the cladding systems are along vertical The cross sectional shape of axle is hexagon, and the hexagon is symmetrical along the longitudinal axis, and the supporting arrangement includes horizontal muscles and bones and pole to vertical bone, To vertical bone be connected for pole by horizontal muscles and bones.
The cladding systems of fusion-fission reaction heap of the invention, the fuel module includes the top fuel mould being sequentially connected Block, middle part fuel module and lower fuel module, top fuel module are trapezium structure, middle part fuel mould with lower fuel module Block is rectangular configuration.
The cladding systems of fusion-fission reaction heap of the invention, the shell of the fuel module including zirconium material, located at outer The coolant pressure pipe in fission fuel and embedded fission fuel in shell, in the top fuel module and lower fuel module 2~6 layers of coolant pressure pipe are embedded with, every layer of coolant pressure pipe inflection shape is arranged in top fuel module and is fired with bottom In material module, the coolant pressure pipe in the middle part fuel module is longitudinally arranged, the top fuel module, middle part fuel mould Coolant pressure pipe in block and lower fuel module is sequentially communicated.
The cladding systems of fusion-fission reaction heap of the invention, the inner fovea part inner surface is longitudinally provided with some for supporting The positioning and guiding dividing plate of fuel module, every piece of positioning and guiding dividing plate is installed along the latitude direction of cladding systems, the positioning Kicker baffle is provided with the water injection hole for connecting engineering path.
The cladding systems of fusion-fission reaction heap of the invention, the product tritium module including section be U-shaped zirconium cladding and Spherical Li4SiO4 proliferating agents, 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, Li4SiO4 proliferating agents, water stream channel are filled with helium passages And helium passages side is provided with import, opposite side is provided with outlet.
The cladding systems of fusion-fission reaction heap of the invention, the product tritium module includes passing through water slowing down cooling tube and helium Tracheae and the top that is sequentially connected produce that tritium module, middle part produce tritium module and tritium module is produced in bottom(103), tritium module is produced on the top It is trapezoidal to produce tritium module with bottom, and it is rectangle that tritium module is produced at middle part.
The cladding systems of fusion-fission reaction heap of the invention, the water slowing down cooling tube includes what is be connected with water stream channel Water inlet pipe and outlet pipe, helium tube include the air inlet pipe and the blast pipe that are connected with helium passages.
The cladding systems of fusion-fission reaction heap of the invention, the fuel module is applied towards on the first wall of plasma There is low activation ferrite/martensite RAFM steel as coating, the thickness of the coating is 8~15mm.
The beneficial effects of the invention are as follows:
1st, 18 valve cladding modulars are set to by by the cladding systems of fusion-fission reaction heap, independent mould is per valve cladding modular Block, enables to cladding systems modularized production and assembling, can reduce the production time, reduces assembly difficulty, and reduction is produced into This;
2nd, single-lobe covering fuel module is the basic structural unit for constituting subcritical energy covering active region, is achieved in neutron times Increase and release nuclear fission energy, be the cartridge of energy covering, coolant pressure is provided with by being embedded in each fuel module Pipe, can be good at ensureing primary Ioops pressure boundary integrality, coolant pressure pipeline is embedded in fuel module and is designed bunchiness Connection communicating structure, is provided with multilayer coolant pressure pipe inflection shape and is arranged in top fuel module and lower fuel module, described Coolant pressure pipe in the fuel module of middle part is longitudinally arranged, so that cooling agent takes away work by these embedded pressure pipes The heat in property area;In order to prevent fission products from being leaked out from fuel module, so fuel module is designed with the sealing of case casket The zirconium cladding of structure, so as to realize the shielding to fuel fission product;
3rd, the product tritium module being provided with ensure that the mutual independence of the water slowing down cooling tube and tritium multiplication agent bead area produced in tritium module, 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 Tritium runner is carried, the utilization of Fusion Neutron is maximized, and reduces the keff needed for realizing expected energy gain and tritium breeding ratio, carried High yield 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 (10)

1. a kind of cladding systems of fusion-fission reaction heap, it is characterised in that including:Some valve cladding modulars, the cladding mode Block splicing is wrapped in outside fusion target room and the cladding systems of 360 ° of formation, and the product tritium module of some connections is included per valve cladding modular (1), some connections fuel module(2)And supporting arrangement(4), the supporting arrangement(4)With towards fusion target chamber center Inner fovea part(401), the inner fovea part(401)Inner surface is coated with product tritium module(1)And fuel module(2), the product tritium module (1)Located at fuel module(2)Outer layer.
2. cladding systems of fusion-fission reaction heap according to claim 1, it is characterised in that the product tritium module(1) With fuel module(2)Between be additionally provided with engineering path(3).
3. cladding systems of fusion-fission reaction heap according to claim 1, it is characterised in that the cladding modular is 18 Valve, the cladding systems are hexagon along the cross sectional shape of the longitudinal axis, and the hexagon is symmetrical along the longitudinal axis, the supporting arrangement(4) Including horizontal muscles and bones(402)With pole to vertical bone(403), horizontal muscles and bones(402)By pole to vertical bone(403)It is connected.
4. cladding systems of fusion-fission reaction heap according to claim 1, it is characterised in that the fuel module(2) Including the top fuel module being sequentially connected(9), middle part fuel module(8)With lower fuel module(7), top fuel module (9)With lower fuel module(7)It is trapezium structure, middle part fuel module(8)It is rectangular configuration.
5. cladding systems of fusion-fission reaction heap according to claim 4, it is characterised in that the fuel module(2) Shell including zirconium material(202), fission fuel in shell(203)With the coolant pressure pipe in embedded fission fuel (201), the top fuel module(9)With lower fuel module(7)Inside it is embedded with 2~6 layers of coolant pressure pipe(201), institute State every layer of coolant pressure pipe inflection shape and be arranged in top fuel module(9)With lower fuel module(7)It is interior, the middle part fuel Module(8)Interior coolant pressure pipe(201)It is longitudinally arranged, the top fuel module(9), middle part fuel module(8)And under Portion's fuel module(7)Interior coolant pressure pipe(201)It is sequentially communicated.
6. cladding systems of fusion-fission reaction heap according to claim 1 and 2, it is characterised in that the inner fovea part (401)Inner surface is longitudinally provided with some positioning and guiding dividing plates for supporting fuel module(5), every piece of positioning and guiding dividing plate (5)Installed along the latitude direction of cladding systems, the positioning and guiding dividing plate(5)It is provided with the water injection hole for connecting engineering path (6).
7. cladding systems of fusion-fission reaction heap according to claim 1 and 2, it is characterised in that the product tritium module (1)It is U-shaped zirconium cladding including section(106)And spherical Li4SiO4Proliferating agent(107), the zirconium cladding(106)Inside it is provided with Some sections are U-shaped dividing plate(109), dividing plate(109)Between form water stream channel(108)And helium passages(105), current lead to Road(108)With helium passages(105)Interval setting, helium passages(105)It is interior filled with Li4SiO4Proliferating agent(107).
8. cladding systems of fusion-fission reaction heap according to claim 7, it is characterised in that the product tritium module(1) Including 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 Module(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, Produce tritium module in middle part(102)It is rectangle.
9. cladding systems of fusion-fission reaction heap according to claim 8, it is characterised in that the water slowing down cooling tube (109)Including with water stream channel(108)The water inlet pipe of connection(110)And outlet pipe(111), helium tube(112)Including with helium Passage(105)The air inlet pipe of connection(113)And blast pipe(114).
10. according to the cladding systems of one of claim 1-9 described fusion-fission reaction heap, it is characterised in that the fuel Module(2)Low activation ferrite/martensite RAFM steel is scribbled on towards the first wall of plasma as coating, the coating Thickness is 8~15mm.
CN201710207659.8A 2017-03-31 2017-03-31 A kind of cladding systems of fusion-fission reaction heap Expired - Fee Related CN106816181B (en)

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
CN109961855A (en) * 2017-12-25 2019-07-02 哈尔滨工业大学 A kind of nuclear fusion first pars intramuralis cooling duct cooling based on eddy flow
CN110569613A (en) * 2019-09-12 2019-12-13 西安交通大学 Method applied to fusion reactor cladding accurate engineering design
CN112259261A (en) * 2020-10-23 2021-01-22 核工业西南物理研究院 Fusion reactor water-cooling liquid lithium lead tritium production blanket module shunting system

Citations (3)

* Cited by examiner, † Cited by third party
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
CN206833929U (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 cladding systems of fusion-fission reaction heap

Patent Citations (3)

* Cited by examiner, † Cited by third party
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
CN206833929U (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 cladding systems of fusion-fission reaction heap

Non-Patent Citations (5)

* Cited by examiner, † Cited by third party
Title
彭先觉: "新型次临界能源堆:聚变+裂变=未来能源发展之路", 《科技日报》 *
曾和荣等: "ITER驱动次临界包壳总体结构概念设计", 《强激光与粒子束》 *
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》 *
盛利: "新设计将铀利用率提高至90%", 《中国矿业报》 *
程和平等: "聚变-裂变混合堆设计研究", 《原子能科学技术》 *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109961855A (en) * 2017-12-25 2019-07-02 哈尔滨工业大学 A kind of nuclear fusion first pars intramuralis cooling duct cooling based on eddy flow
CN109961855B (en) * 2017-12-25 2020-11-13 哈尔滨工业大学 Nuclear fusion first wall internal cooling channel based on rotational flow cooling
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
CN110569613A (en) * 2019-09-12 2019-12-13 西安交通大学 Method applied to fusion reactor cladding accurate engineering design
CN112259261A (en) * 2020-10-23 2021-01-22 核工业西南物理研究院 Fusion reactor water-cooling liquid lithium lead tritium production blanket module shunting system
CN112259261B (en) * 2020-10-23 2022-05-17 核工业西南物理研究院 Fusion reactor water-cooling liquid lithium lead tritium production blanket module shunting system

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