CN108417283A - Underground neutron energy power station - Google Patents

Underground neutron energy power station Download PDF

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Publication number
CN108417283A
CN108417283A CN201810270105.7A CN201810270105A CN108417283A CN 108417283 A CN108417283 A CN 108417283A CN 201810270105 A CN201810270105 A CN 201810270105A CN 108417283 A CN108417283 A CN 108417283A
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CN
China
Prior art keywords
underground
power station
energy power
neutron energy
heat exchanger
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Granted
Application number
CN201810270105.7A
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Chinese (zh)
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CN108417283B (en
Inventor
何满潮
吴宜灿
杨晓杰
汪建业
乔亚飞
王芳
王�琦
柏云清
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Individual
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Individual
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Priority to CN201810270105.7A priority Critical patent/CN108417283B/en
Publication of CN108417283A publication Critical patent/CN108417283A/en
Priority to PCT/CN2019/079798 priority patent/WO2019184932A1/en
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Publication of CN108417283B publication Critical patent/CN108417283B/en
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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01KSTEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K9/00Plants characterised by condensers arranged or modified to co-operate with the engines
    • F01K9/003Plants characterised by condensers arranged or modified to co-operate with the engines condenser cooling circuits
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22DPREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D11/00Feed-water supply not provided for in other main groups
    • F22D11/02Arrangements of feed-water pumps
    • F22D11/06Arrangements of feed-water pumps for returning condensate to boiler
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24HEATING; RANGES; VENTILATING
    • F24DDOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
    • F24D3/00Hot-water central heating systems
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28DHEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D21/0001Recuperative heat exchangers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B3/00Low temperature nuclear fusion reactors, e.g. alleged cold fusion reactors
    • G21B3/006Fusion by impact, e.g. cluster/beam interaction, ion beam collisions, impact on a target
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24HEATING; RANGES; VENTILATING
    • F24DDOMESTIC- OR SPACE-HEATING SYSTEMS, e.g. CENTRAL HEATING SYSTEMS; DOMESTIC HOT-WATER SUPPLY SYSTEMS; ELEMENTS OR COMPONENTS THEREFOR
    • F24D2200/00Heat sources or energy sources
    • F24D2200/16Waste heat
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28DHEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0054Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications
    • 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
    • Y02E20/00Combustion technologies with mitigation potential
    • Y02E20/14Combined heat and power generation [CHP]
    • 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
    • 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
    • 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
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Water Supply & Treatment (AREA)
  • Particle Accelerators (AREA)

Abstract

The present invention provides a kind of underground neutron energy power station, in the chamber located underground of underground neutron energy power station comprising:Neutron source system, one end of chamber located underground, neutron source system have the ion beam tube for emitting ion;Energy production system, the lower section of chamber located underground, energy production system have the reaction vessel for placing reactor core, coupled structure are sealedly connected between reaction vessel and ion beam tube;Electricity generation system, the other end of chamber located underground, electricity generation system are connected with energy production system;Waste heat collection and utilization system, the other end of chamber located underground, waste heat collection and utilization system are connected with energy production system, electricity generation system respectively.The underground neutron energy power station of the present invention can make full use of fuel to be powered and heat supply, and fuel availability is high, and the underground neutron energy power station is located underground, elongated arrangement, and key equipment miniaturization can permanently seal fuel up for safekeeping, securely and reliably.

Description

Underground neutron energy power station
Technical field
The present invention relates to energy environments and underground space field more particularly to a kind of underground neutron energy power station.
Background technology
In recent years, the environmental pollution in China is increasingly severe, and a cities up to a hundred are perplexed by haze.By to historical data Analysis and investigation find that the basic reason that haze problem generates is that coal consumption accounting is excessively high.2015, coal in China consumption Accounting about 64% is the main reason for leading to China's environmental problem and haze weather.The experience for using for reference Germany and Britain, is asked for Environment control Topic, it is necessary to reduce the consumption accounting of coal.When coal consumption accounting is reduced to 35%, air quality is clearly better; When coal consumption accounting is reduced to 25%, the environmental problems such as haze substantially eliminate.30% energy is substituted for that purpose it is necessary to need to find The clean energy resource in source.
Traditional clean energy resource includes wind energy, solar energy, water energy and geothermal energy etc..But wind energy and solar energy are by environment item Part restricts, and utilization rate of equipment and installations is low, and current technology is unsatisfactory for the condition of extensive development.Water power is due to distribution of water resources unevenness Even, potentiality to be exploited is limited, and there is the risk to ecological environment destruction.Geothermal energy belongs to novel energy, is still in Preliminary Exploitation Stage, current technology utilize shallow layer geothermal energy, do not have the possibility for providing extensive energy supply mostly.According to long in China Phase plans that the non-fossil energy in China cannot meet the possibility of extensive Substitute coal resource in the year two thousand thirty accounting about 20%.
Nuclear power has a possibility for providing the extensive energy as a kind of novel energy, but its development but encounter it is huge Resistance:(1) nuclear accident influences huge, such as Japanese nuclear island accident;(2) China's uranium ore resource lacks, the fuel mould of enriched uranium Formula is difficult to meet sustainable development;(3) there are height putting property nuke rubbish, have long-term hazards, and later stage disposal costs are higher.Foundation China's development plan, China's nuclear power account for the 8%~10% of gross generation, there is no carry in 1.5 hundred million kilowatts of the year two thousand thirty total installed capacity amount For the possibility of 30% energy.
In conclusion there is no the possibilities for providing 30% alternative energy source for currently used clean energy resource.
Invention content
The object of the present invention is to provide a kind of underground neutron energy power station, fuel can be made full use of to be powered and heat supply, Fuel availability is high, in the underground neutron energy power station space located underground, elongated arrangement, and key equipment miniaturization, energy Permanently seal fuel up for safekeeping, securely and reliably.
Following technical proposal can be used to realize in the above-mentioned purpose of the present invention:
The present invention provides a kind of underground neutron energy power station, in the chamber located underground of the underground neutron energy power station comprising:
Neutron source system, is located at one end of the underground chamber, and the neutron source system has for emitting ion Ion beam tube;
Energy production system is located at the lower section of the underground chamber, and the energy production system, which has, places reactor core Reaction vessel is sealedly connected with coupled structure between the reaction vessel and the ion beam tube;
Electricity generation system is located at the other end of the underground chamber, the electricity generation system and the energy production system phase Even;
Waste heat collection and utilization system is located at the other end of the underground chamber, the waste heat collection and utilization system difference It is connected with the energy production system, the electricity generation system.
In embodiments of the present invention, the lower section of the underground chamber is equipped with anti-nuclein migration barriers, the energy Generation system is located in the anti-nuclein migration barriers.
In embodiments of the present invention, the anti-nuclein migration barriers include:
Artificial barrier structure in the underground chamber lower part is set, and the artificial barrier structure has bottom wall, week Side wall and roof, are formed with accommodating chamber between the bottom wall, all side walls and the roof, the energy production system is placed In the accommodating chamber, the bottom wall, all side walls and the roof all have the lead powder coagulation set gradually from the inside to the outside Soil layer, argillic horizon and reinforced concrete floor;
Grouting layer is disposed around the outside of the artificial barrier structure;
Casing, is located at the outside of the grouting layer, and the casing has country rock thickness.
In embodiments of the present invention, the roof is connected with the bottom wall of the underground chamber, the bottom wall it is described It is respectively equipped with the grouting layer on the outside of the reinforced concrete floor of the outside of reinforced concrete floor and all side walls.
In embodiments of the present invention, the argillic horizon includes ball clay internal layer and clay powder outer layer, the ball clay Internal layer is spliced to form by multiple ball clays, and the clay powder outer layer is folded in the ball clay internal layer and the reinforced concrete floor Between.
In embodiments of the present invention, the argillic horizon is spliced to form by multiple ball clays.
In embodiments of the present invention, the ball clay internal layer of the bottom wall includes that multiple torus and setting exist Central block in the middle part of the multiple torus, the torus are spliced to form by multiple arcs block.
In embodiments of the present invention, the argillic horizon of the bottom wall includes multiple torus and is arranged described Central block in the middle part of multiple torus, the torus are spliced to form by multiple arcs block.
In embodiments of the present invention, the central block is square block;Alternatively, the central block is by two Trapezoidal block splicing composition.
In embodiments of the present invention, vertical range of the underground chamber apart from ground is not less than 70m.
In embodiments of the present invention, the coupled structure includes:
Target assembly, with line pipe and the target ontology being connected on the line pipe, the line pipe and the ion Beam tube is connected;
Head cover is sealedly connected on the reaction vessel, and the head cover has at least two lamina tectis mutually spliced, The connecting hole worn for the line pipe is formed between at least two lamina tecti.
In embodiments of the present invention, there is the head cover connected structure, at least two lamina tecti to pass through described Connected structure is mutually stitched together.
In embodiments of the present invention, the connected structure includes multiple fins and multiple grooves, and the fin is inserted into In the groove, the multiple fin and the multiple groove are arranged on the end face that at least two lamina tecti mutually splices.
In embodiments of the present invention, the lamina tecti is two, and the lamina tecti is semicircle, two head covers Plate make-up forms the head cover.
In embodiments of the present invention, the outer cover of the line pipe is equipped with the double-deck outer tube, and the bilayer outer tube has Vacuum chamber.
In embodiments of the present invention, the line pipe has been externally wrapped with cooling tube, and the cooling tube is located at described Between the double-deck outer tube and the line pipe.
In embodiments of the present invention, the outside of the cooling tube is equipped with reflectance coating.
In embodiments of the present invention, the outer cup of the energy production system is equipped with containment, and the line pipe is logical Fixation steel plate is crossed to be connected on the containment.
In embodiments of the present invention, the target ontology is inserted into the reactor core of the energy production system.
In embodiments of the present invention, the waste heat collection and utilization system includes:
Main electricity generation system waste heat acquisition utilizes circuit, has the First Heat Exchanger being connected with the electricity generation system, described First Heat Exchanger is connected with the first hot trap;
The acquisition of shielding construction waste heat utilizes circuit, has heat exchanger tube, the second heat exchanger and the second hot trap being sequentially connected, The heat exchanger tube is arranged in the peripheral side of the energy production system.
In embodiments of the present invention, the waste heat collection and utilization system further includes:Residual heat of nuclear core acquisition utilizes circuit, There is cooling water tank, third heat exchanger and the third hot trap being sequentially connected, the cooling water tank to be arranged in the energy production for it The lower part of system.
In embodiments of the present invention, the energy production system is placed on anti-nuclein migration barriers located underground Interior, there is the anti-nuclein migration barriers accommodating chamber, the electricity generation system to have steam generator, the steam turbine being sequentially connected And generator, the steam generator are connected with the energy production system, are located at the top of the accommodating chamber.
In embodiments of the present invention, the heat exchanger tube includes the circumferential heat exchanger tube being connected and vertical heat exchanger tube, institute All side-walls that vertical heat exchanger tube is located at the accommodating chamber are stated, the circumferential direction heat exchanger tube is embedded in the anti-nuclein migration barriers In.
In embodiments of the present invention, the vertical heat exchanger tube has the vertical water inlet pipe being connected and vertical water outlet Pipe, the circumferential direction heat exchanger tube have circumferential water inlet pipe and circumferential outlet pipe, the circumferential direction water inlet pipe and the vertical water inlet pipe phase Even, the circumferential direction outlet pipe is connected with the vertical outlet pipe.
In embodiments of the present invention, the vertical outlet pipe is arranged close to the anti-nuclein migration barriers, described Vertical water inlet pipe is arranged close to the energy production system.
In embodiments of the present invention, pass through the first pipeline phase between the cooling water tank and the third heat exchanger Even, it is connected by the second pipeline between the third heat exchanger and the third hot trap, first pipeline is equipped with for controlling The first circulation of circulating water velocity processed pumps.
In embodiments of the present invention, it is connected by third pipeline between the heat exchanger tube and second heat exchanger, It is connected by the 4th pipeline between second heat exchanger and second hot trap, the third pipeline is equipped with to follow for controlling The second circulation of ring water speed pumps.
In embodiments of the present invention, it is connected by the 5th pipeline between the steam generator and the steam turbine, The First Heat Exchanger is connected on the 5th pipeline, passes through the 6th pipe between the First Heat Exchanger and first hot trap Road is connected.
In embodiments of the present invention, first hot trap, second hot trap and the third hot trap are separately connected There is external heating system.
In embodiments of the present invention, the neutron source system includes the ion source being sequentially connected, accelerator and described Ion beam tube.
The characteristics of underground neutron energy power station of the present invention and advantage are:The underground neutron energy power station have fuel utilization it is high, The advantage that waste material is few and radioactivity is low, degree of safety is high, and it is distributed in underground, elongated arrangement, key equipment miniaturization, profit In in the distributed construction of whole nation progress.The fuel rate in the underground neutron energy power station is high, exists and provides current AND ENERGY RESOURCES CONSUMPTION IN CHINA amount 30% possibility, and its cost of electricity-generating is also relatively low.The fuel ratio tradition nuclear power station in underground neutron energy power station is easily obtained, and can Using conventional nuclear power waste material as fuel, the defect of fuel poverty is not present.Underground neutron energy power station is set to underground, and Provided with anti-nuclein migration barriers, underground neutron energy power plant construction is realized, operation, retired and waste disposal integration are set It sets, reduces whole construction investment.
Description of the drawings
To describe the technical solutions in the embodiments of the present invention more clearly, make required in being described below to embodiment Attached drawing is briefly described, it should be apparent that, drawings in the following description are only some embodiments of the invention, for For those of ordinary skill in the art, without creative efforts, other are can also be obtained according to these attached drawings Attached drawing.
Fig. 1 is the main structure diagram in the underground neutron energy power station of the present invention.
Fig. 2 is the overlooking structure diagram in the underground neutron energy power station of the present invention.
Fig. 3 is the structural schematic diagram of the coupled structure of the present invention.
Fig. 4 is the schematic diagram of the connected structure of the head cover of the present invention.
Fig. 5 is the stereogram of the head cover of the present invention.
Fig. 6 is the structure chart of the target assembly of the present invention.
Fig. 7 is the main structure figure of the anti-nuclein migration barriers of the present invention.
Fig. 8 is the overlooking structure figure of the anti-nuclein migration barriers of the present invention.
Fig. 9 is the structural schematic diagram of an embodiment of the argillic horizon of the anti-nuclein migration barriers of the present invention.
Figure 10 is the structural schematic diagram of another embodiment of the argillic horizon of the anti-nuclein migration barriers of the present invention.
Figure 11 is the structural schematic diagram of an embodiment of the bottom wall of the argillic horizon of the anti-nuclein migration barriers of the present invention.
Figure 12 is the structural schematic diagram of another embodiment of the bottom wall of the argillic horizon of the anti-nuclein migration barriers of the present invention.
Figure 13 is the structural schematic diagram of the waste heat collection and utilization system of the present invention.
Figure 14 is the structural schematic diagram of the heat exchanger tube of the waste heat collection and utilization system of the present invention.
Figure 15 is the Longitudinal cross section schematic of an embodiment of the underground chamber of the present invention.
Figure 16 is the Longitudinal cross section schematic of another embodiment of the underground chamber of the present invention.
Drawing reference numeral explanation:1, neutron source system;11, ion beam tube;12, ion source;13, accelerator;2, energy production System;21, reaction vessel;211, reactor core;3, waste heat collection and utilization system;31, main electricity generation system waste heat acquisition utilizes circuit; 311, First Heat Exchanger;312, the 6th pipeline;3121, water inlet pipe;3122, outlet pipe;32, shielding construction waste heat acquisition utilizes back Road;321, heat exchanger tube;3211, circumferential heat exchanger tube;32111, circumferential water inlet pipe;32112, circumferential outlet pipe;3212, vertical heat exchange Pipe;32121, vertical water inlet pipe;32122, vertical outlet pipe;322, the second heat exchanger;323, third pipeline;3231, water inlet pipe; 3232, outlet pipe;3233, second circulation pumps;324, the 4th pipeline;3241, outlet pipe;3242, water inlet pipe;33, residual heat of nuclear core Acquisition utilizes circuit;331, cooling water tank;332, third heat exchanger;333, the first pipeline;3331, water inlet pipe;3332, it is discharged Pipe;3333, first circulation pumps;334, the second pipeline;3341, water inlet pipe;3342, outlet pipe;34, hot trap;341, circuit;4, it sends out Electric system;41, steam generator;42, steam turbine;43, generator;44, the 5th pipeline;441, outlet pipe;442, water inlet pipe; 37, heating system;5, coupled structure;51, target assembly;511, line pipe;512, target ontology;513, the double-deck outer tube;514, vacuum Chamber;515, cooling tube;516, sealing flange;517, fixation steel plate;52, head cover;521, lamina tecti;522, connecting hole;523, it inserts Binding structure;5231, fin;5232, groove;53, containment;6, anti-nuclein migration barriers;61, artificial barrier structure; 611, bottom wall;612, all side walls;613, roof;614, accommodating chamber;615, lead powder concrete layer;616, argillic horizon;6161, clay Block internal layer;6161a, arc block;6161b, arc block;6161c, class arc block;6161d, trapezoidal block;6161d, just Rectangular block;6162, clay powder outer layer;617, reinforced concrete floor;618, grouting layer;62, casing;7, shaft structure;8、 Ventilation distribution system;81, electrical corollary apparatus;82, ventilation waterworks;9, fuel storage system;10, underground chamber;101、 Main tunnel structure body;102, branch's tunnel structure body;103, shield door;104, bottom wall;105, neutron energy chamber;106, thermoelectricity joins For chamber.
Specific implementation mode
Following will be combined with the drawings in the embodiments of the present invention, and technical solution in the embodiment of the present invention carries out clear, complete Site preparation describes, it is clear that described embodiments are only a part of the embodiments of the present invention, instead of all the embodiments.It is based on Embodiment in the present invention, it is obtained by those of ordinary skill in the art without making creative efforts every other Embodiment shall fall within the protection scope of the present invention.
As depicted in figs. 1 and 2, the present invention provides a kind of underground neutron energy power station, and the underground neutron energy power station is located at ground In lower chamber 10 comprising:
Neutron source system 1, be located at the underground chamber 10 one end, the neutron source system 1 have for emit from The ion beam tube 11 of son;
Energy production system 2 is located at the lower section of the underground chamber 10, and the energy production system 2, which has, places heap The reaction vessel 21 of core 211, is sealedly connected with coupled structure 5 between the reaction vessel 21 and the ion beam tube 11;
Electricity generation system 4 is located at the other end of the underground chamber 10, the electricity generation system 4 and the energy production system System 2 is connected;
Waste heat collection and utilization system 3 is located at the other end of the underground chamber 10, the waste heat collection and utilization system 3 It is connected respectively with the energy production system 2, the electricity generation system 4.
Specifically, underground chamber 10 has main tunnel structure body 101 and is connected to main 101 one end of tunnel structure body extremely Few branch's tunnel structure body 102, at least one branch's tunnel structure body 102 are connected with main tunnel structure body 101.In master The junction of tunnel structure body 101 and branch's tunnel structure body 102 is equipped with shaft structure 7, the shaft structure 7 respectively with main tunnel Structure 101 is connected with branch tunnel structure body 102, and worker can pass through the shaft structure 7 and enter underground chamber 10.The main tunnel Hole structure 101 is the core chamber in underground neutron energy power station, is substantially in strip chamber structure, the main tunnel structure body 101 are arranged horizontally in below ground, and the vertical range H apart from ground is not less than 70m, that is, the main tunnel structure body 101 Vertical range H of the vault apart from ground is not less than 70m.In the present invention, as shown in figure 15, the main tunnel knot of the underground chamber 10 The vertical sectional shape of structure body 101 and branch's tunnel structure body 102 can be circular ring shape;Alternatively, as shown in figure 16, the underground chamber 10 Main tunnel structure body 101 and the vertical sectional shape of branch's tunnel structure body 102 can be the shape of a hoof;Certainly, implement in others In example, the main tunnel structure body 101 of the underground chamber 10 and the longitudinal section of branch's tunnel structure body 102 are alternatively other shapes, It is not limited herein.The underground neutron energy power station is placed in underground chamber 10, is integrally located at underground 70m hereinafter, can be effective Completely cut off influence of the underground neutron energy power station operation to human residential environment.
One end of the main tunnel structure body 101 of 1 chamber 10 located underground of neutron source system comprising the ion being sequentially connected Source 12, accelerator 13 and ion beam tube 11.The neutron source system 1 is used to provide ion beam for energy production system 2, in the present invention In, the parallel ion beam current of single beam or multi beam which is emitted by ion source 12, under the action of accelerator 13 It is accelerated as high-speed ion line, is exported later by ion beam tube 11, target is bombarded using high-speed ion line, generates neutron, The release rate of source energy can be effectively improved, in the present invention, which can be deuterium ion.The neutron source system 1 can adopt The gaseous state target neutron source disclosed in Chinese Patent Application No. CN201710078364.5.In the present invention, which answers Certain levelness is kept in underground chamber 10.
The lower section of 2 chamber 10 located underground of energy production system has the reaction vessel 21 for placing reactor core 211, the heap Core 211 is using lead or lead bismuth alloy as coolant, which is the liquid/solid body for being enclosed in fuel periphery, due to using lead Or lead bismuth alloy greatly reduces the volume of reactor core 211 as coolant.
It is connected by the sealing of coupled structure 5 between the reaction vessel 21 and the ion beam tube 11 of neutron source system 1.In this hair In bright, as shown in figure 3, the coupled structure 5 is connected between neutron source system 1 and energy production system 2, the coupled structure 5 packet Target assembly 51 and head cover 52 are included, wherein:The target ontology 512 that target assembly 51 has line pipe 511 and is connected on line pipe 511, The line pipe 511 is connected with ion beam tube 11;Head cover 52 is sealedly connected on reaction vessel 21, which has mutually splicing At least two lamina tectis 521, be formed with the connecting hole 522 worn for line pipe 511 between at least two lamina tectis 521. In the present invention, which is tritium target.
After the ion beam sent out from neutron source system 1 is by ion beam tube 11 and line pipe 511, bombardment is connected to line The target ontology 512 of 511 end of pipe and fusion forms neutron, which react with the reactor core 211 in energy production system 2 generates newly Easy fissioner and realize that fission reaction generates a large amount of energy.Fusion reaction production occurs in ion beam bombardment target ontology 512 During raw neutron, the high temperature heat more than 300 DEG C will produce.
The coupled structure 5 is connected between neutron source system 1 and energy production system 2, compact-sized, the coupled structure 5 head cover 52 can be detachably connected with target assembly 51, reloads or uncap repair when energy production system 2 uncap When Deng operating, head cover 52 is directly dismantled, avoids target assembly 51 from the dismantling operation on energy production system 2 so that behaviour Work is easier, which can be between the effective guarantee target assembly 51 being connected with neutron source system 1 and energy production system 2 Connective stability.
Specifically, please refer to shown in Fig. 6, the target assembly 51 of the coupled structure 5 has the line passed through for ion beam Pipe 511, target ontology 512 are connected to the end of line pipe 511;In the present invention, it is equipped in the outer cover of line pipe 511 double-deck outer Pipe 513, the bilayer outer tube 513 have vacuum chamber 514, can one by vacuum chamber 514 by the vaccum-pumping equipment outside piping connection The straight condition of high vacuum degree environment for maintaining vacuum chamber 514, the vacuum chamber 514 be used to block 51 outside of isolation target assembly hot environment and Heat exchange between target ontology 512.
Further, be additionally provided with cooling tube 515 in the outside of line pipe 511, the cooling tube 515 be located at line pipe 511 with Between the double-deck outer tube 513, in the present embodiment, cooling tube 515 is connected to the outer wall of line pipe 511 in a manner of spiral winding On, which carries out that in cooling treatment, such as the cooling tube 515 coolant can be passed through for halved tie flow tube 511, passes through Fluxion strap of the coolant in cooling tube 515 walks the heat that ion beam bombardment generates on target ontology 512.In the present embodiment, The outer wall of the cooling tube 515 is equipped with reflectance coating, which is used to generate the high temperature environment of 51 outside of target assembly Radiant heat reflect back.Certainly, in other implementations, other refrigeration knots can be also equipped in the outside of line pipe 511 Structure is taken away the heat that ion beam bombardment generates on target ontology 512 as long as can realize, is not limited herein.
As shown in Figure 4 and Figure 5, the head cover 52 of coupled structure 5 is made of the splicing of at least two lamina tectis 521, in this implementation In mode, which has connected structure 523, and at least two lamina tecti 521 is by the mutually splicing of connected structure 523 one It rises.
Specifically, the connected structure 523 includes multiple fins 5231 and multiple grooves 5232, which is inserted into groove In 5232, multiple fins 5231 and multiple grooves 5232 are arranged on the end face that at least two lamina tectis, 521 phase is spliced.
In an embodiment of the present invention, which is two, which is semicircle, two lamina tectis 521 make-ups form circular head cover 52.5231 He of multiple fins is respectively equipped on the splicing end face of two 521 make-ups of lamina tecti Multiple grooves 5232, when two lamina tectis 521 are buckled togather, multiple fins 5231 on one of lamina tecti 521 are inserted Enter in multiple grooves 5232 on another lamina tecti 521, the shielding action of two 521 junctions of lamina tecti can be enhanced in this way. Certainly, in other implementations, head cover 52 also can be by three lamina tectis, 521, four lamina tectis 521 or more lamina tecti 521 splicing compositions, are not limited herein.The head cover 52 of the present invention lock out operation can be carried out by lifting machine and combination is installed, Without influencing target assembly 51.
It is formed with the connecting hole 522 worn for line pipe 511 between at least two lamina tectis 521 of the head cover 52, at this In embodiment, it is set between the double-deck outer tube 513 outside line pipe 511 and connecting hole 522 and is equipped with multiple sealing rings, by more A sealing ring realizes the mechanical static seal between target assembly 51 and head cover 52.
The head cover 52 is sealedly connected on the reaction vessel 21 of energy production system 2, the reactor core 211 in reaction vessel 21 with Reaction vessel 21 is installed with one heart, in the reserved vacancy in 211 center of reactor core, the target ontology 512 for installing target assembly 51, namely Target ontology 512 is inserted into reactor core 211.In the present embodiment, the outer diameter of the target ontology 512 of target assembly 51 is less than reactor core 211 A fuel assembly size, which can replace a fuel assembly, in one embodiment, target sheet The outer diameter of body 512 is not more than 125mm, is mounted on the center position of reactor core 211.
In the present invention, which is connected to by sealing flange 516 on head cover 52.Further, the energy volume production The outer cup of raw system 2 is equipped with containment 53, which is round deep head cover, is made of armored concrete, the safety Shell 53 is vertically connected on the concentric installation of head cover 52, reaction vessel 21 and reactor core 211, the line pipe 511 by fixation steel plate 517 On containment 53.
The coupled structure 5 uses 52 separation design of head cover, when uncapping operation every time, in the neutron energy power station of underground The particularity that component system 1 and energy production system 2 couple, can avoid the operation bidirectional of target pair device 51, it is only necessary to simple Carry out head cover 52 operate;In addition, being tied by increasing vacuum chamber 514 in target assembly 51, and by the entirety of target assembly 51 Structure is designed as the outer diameter of long cartridge type and target ontology 512 less than a fuel assembly size of reactor core 211, can make 51 work of target assembly Make high temperature environment when energy production system 2 is run, enable to couple with energy production system 2 to form operational safety can It leans on, the neutron source system 1 that resource utilization is high.
According to embodiment of the present invention, the lower section of the underground chamber 10 is equipped with anti-nuclein migration barriers 6, the energy Amount generation system 2 is located in anti-nuclein migration barriers 6.
As shown in Figure 7 and Figure 8, which includes:Artificial barrier in 10 lower part of underground chamber is set Structure 61, the artificial barrier structure 61 have bottom wall 611, all side walls 612 and a roof 613, the bottom wall 611, described Accommodating chamber 614, the bottom wall 611, all side walls 612 and the roof are formed between all side walls 612 and the roof 613 613 all have the lead powder concrete layer 615, argillic horizon 616 and reinforced concrete floor 617 set gradually from the inside to the outside;Grouting layer 618, it is disposed around the outside of the artificial barrier structure 61;That is, the grouting layer 618 is in the outer of artificial barrier structure 61 Side, which is formed, to be closed.Casing 62, is located at the outside of the grouting layer 618, and the casing 62 has country rock thickness.
Specifically, the energy production system 2 in underground neutron energy power station is positioned over the accommodating chamber of the artificial barrier structure body 61 In 614, in the present invention, which can be that cylindrical, cuboid or the polygon prism bodily form certainly should Artificial barrier structure 61 can also be designed as other structures shape, not be limited herein.
The bottom wall 611 of the artificial barrier structure body 61, all side walls 612 and roof 613 all have and set gradually from the inside to the outside Lead powder concrete layer 615, argillic horizon 616 and reinforced concrete floor 617.Wherein, in the present invention, in order to making artificial barrier Energy production system 2 in structure 61 is swapped with extraneous energy or substance, lead powder can be arranged on the periphery of roof 613 Concrete layer 615, and the middle part of roof 613 can be not provided with lead powder concrete layer 615, not be limited herein.The roof 613 and ground The bottom wall 104 of lower chamber 10 is connected.
Further, which is embedded in casing 62, in artificial barrier structure 61 and country rock Grouting layer 618 is equipped between layer 62.Specifically, the reinforced concrete floor 617 of the bottom wall 611 of the artificial barrier structure body 61 is outer The outside of the reinforced concrete floor 617 of side and all side walls 612 is equipped with the grouting layer 618.
The group of lead powder concrete layer 615, argillic horizon 616, reinforced concrete floor 617 and grouting layer 618 is specifically described below At and structure:
The lead powder concrete layer 615 participates in lead powder by the concrete of C40 or more labels and is made, and lead powder participates in ratio root It is determined according to the power of energy production system, but usually the amount of participating in of lead powder is not to be exceeded the 20% of cementitious material, avoids its right The influence of concrete strength and working performance.In the present embodiment, the thickness of the lead powder concrete layer 615 is 50cm~100cm, The thickness of the lead powder concrete layer 615 is not limited to this, and thickness should be suitable with the increase of underground neutron energy Power Plant Design power Work as increase.The gamma shielding of lead powder in the lead powder concrete layer 615 is good, and thermal contact can be good.The lead powder concrete layer 615 is led It is used to support the energy production system 2 in underground neutron energy power station, and effectively transmits the waste heat of energy production system 2, simultaneously also It can be effectively prevent the infiltration of underground water, effectively shield remaining ray and radioactive element.In other embodiments, the lead Powder concrete layer 615 can also be replaced by other radiation shield concrete layers, such as participate in the radiation shield concrete of weight strength sand Deng not being limited herein.
The argillic horizon 616 is arranged in the outside of lead powder concrete layer 615, and the clay selected should have good heat transfer The features such as performance, good ionic adsorption and certain expansion self-enclosed property, such as clay that the argillic horizon 616 is selected For bentonite etc..The exclusion of energy production system waste heat can be effectively ensured in the 616 good heat conductivility of argillic horizon, good Ionic adsorption can effectively hinder isotopic ion to external migration, expand self-enclosed property can prevent underground water to Interior flowing, ensures that the operation security of energy production system and isolation is contacted with extraneous.In the present embodiment, the clay The thickness of layer 616 is 30cm~40cm, and thickness should suitably increase with the increase of underground neutron energy Power Plant Design power.
In an embodiments possible of argillic horizon 616, as shown in figure 9, the argillic horizon 616 includes ball clay internal layer 6161 With clay powder outer layer 6162, which is spliced to form by multiple ball clays, which is folded in Between ball clay internal layer 6161 and reinforced concrete floor 617.In the present embodiment, when the cross section of the artificial barrier structure body 61 For circular ring shape when, multiple ball clays of the ball clay internal layer 6161 of all side walls 612 can be arc block, as shown in figure 11, the bottom of at In one possible embodiments of wall 611, multiple ball clays of the ball clay internal layer 6161 of the bottom wall 611 include multiple arcs block 6161a, multiple arcs block 6161b, multiple class arc block 6161c and square block 6161d namely the bottom wall 611 can For set gradually from outside to inside the torus being spliced to form by multiple arcs block 6161a, by multiple arcs block 6161b spell It connects the torus to be formed, the torus being spliced to form by multiple class arc block 6161c and the square block at middle part is set 6161d is spliced to form;Alternatively, in another possible embodiments of bottom wall 611, as shown in figure 12, in the ball clay of the bottom wall 611 Multiple ball clays of layer 6161 include multiple arcs block 6161a, multiple arcs block 6161b, multiple class arc block 6161c Can be to be set gradually from outside to inside by multiple arcs block 6161a spellings with two trapezoidal block 6161d namely the bottom wall 611 It connects the torus to be formed, the torus being spliced to form by multiple arcs block 6161b, spliced by multiple class arc block 6161c The torus of formation and two trapezoidal block 6161d being arranged at middle part are spliced to form;The artificial barrier structure body 61 it is transversal Face is alternatively other shapes, such as polygon or irregular polygon etc., is not limited herein.Meanwhile argillic horizon 616 is multiple The shape of ball clay is also specifically divided with the concrete shape of argillic horizon 616.
In this embodiment, in construction, the clay powder outer layer 6162 for the bottom wall 611 that should first construct, then assembled bottom wall 611 Ball clay internal layer 6161, and after combining the ball clay internal layer 6161 of assembled all side wall 612, in the ball clay of all side walls 612 Annular space is formed between layer 6161 and reinforced concrete floor 617, it is viscous to be formed finally to backfill the annular space with clay powder Native powder outer layer 6162.After having moisture to penetrate into argillic horizon 616, due to the self-enclosed property of the expansion of clay, self inflation can occur, And then the gap between the ball clay adjacent two-by-two in ball clay internal layer 6161 is filled, and low-moisture infiltration system effectively drops Number, hinders the infiltration of underground water.The argillic horizon 616 has good ion adsorption capacity, and energy production is escaped out there is nucleic When system, it can be effectively adsorbed in argillic horizon 616, prevent it to external migration.
In another embodiments possible of argillic horizon 616, as shown in Figure 10, which is spelled by multiple ball clays It connects to be formed.In the present embodiment, when the cross section of the artificial barrier structure body 61 is circular ring shape, the argillic horizon of all side walls 612 616 multiple ball clays can be arc block, as shown in figure 11, in a possible embodiments of bottom wall 611, the bottom wall 611 Multiple ball clays of argillic horizon 616 include multiple arcs block 6161a, multiple arcs block 6161b, multiple class arc blocks 6161c and square block 6161d namely the bottom wall 611 can be to be set gradually from outside to inside by multiple arcs block 6161a The torus that is spliced to form, the torus being spliced to form by multiple arcs block 6161b are spelled by multiple class arc block 6161c The square block 6161d for connecing the torus to be formed and being arranged at middle part is spliced to form;Alternatively, in the another feasible of bottom wall 611 In embodiment, as shown in figure 12, multiple ball clays of the argillic horizon 616 of the bottom wall 611 include multiple arcs block 6161a, more A arc block 6161b, multiple class arc block 6161c and two trapezoidal block 6161d namely the bottom wall 611 can be from outer It is spliced to form to the interior torus being spliced to form by multiple arcs block 6161a set gradually, by multiple arcs block 6161b Torus, the torus that is spliced to form by multiple class arc block 6161c and two trapezoidal block 6161d at middle part are set It is spliced to form;The cross section of the artificial barrier structure body 61 is alternatively other shapes, such as polygon or irregular polygon etc., It is not limited herein.Meanwhile the shape of multiple ball clays of argillic horizon 616 also carries out specifically with the concrete shape of argillic horizon 616 It divides.
The argillic horizon 616 is since ball clay assembly is inevitably present the gap between block, these gaps are to entirely shielding Barrier system is unfavorable, for this purpose, the composite structure layer of ball clay internal layer 6161 and clay powder outer layer 6162 should be used preferentially.
The reinforced concrete floor 617 is disposed around the outside of argillic horizon 616, primarily serves stabilizing surrounding rock and the work of waterproof With, which should be made of high performance concrete, be used primarily to ensure the stabilization and safety of underground chamber 10, Simultaneously it is possible to prevente effectively from the infiltration of extraneous underground water.In the present embodiment, the thickness of the reinforced concrete floor 617 be 50cm~ 70cm.The reinforced concrete floor that the reinforced concrete floor 617 can refer to general underground chamber is designed construction, usually, When design, all loads caused by country rock are should bear.In addition, in the neutron energy power station of underground, the reinforced concrete floor 617 It is made of the concrete marked as C35 or more.
The grouting layer 618 is arranged in the outside of reinforced concrete floor 617, and main function is the infiltration for reducing casing 62 Coefficient improves the density of casing 62, and should use the higher slurries of viscous mineral content, improves the ion of casing 62 Adsorption capacity, another effect of grouting layer 618 are to improve the degree of stability of country rock when enclosing Rock Slide Stability deficiency.The slip casting Layer 618 should use slurries to carry out slip casting on 10 periphery of underground chamber, form closed injecting cement paste, can volume production for further completely cutting off The transmission of moisture, nucleic and ambient systems inside raw system 2.In the present embodiment, the construction of the grouting layer 618 can be in reinforcing bar Before or after concrete layer 617 is constructed.Stablize preferable place in casing 62, should preferentially construct grouting layer 618, can be on ground After the lower periphery of lower chamber 10 uniformly sets Grouting Pipe, slip casting is carried out using suitable grouting pressure, and effectively control slip casting Amount;In the place that 62 stability of casing is poor, preferential construction reinforced bar concrete layer 617 is answered, then again under underground chamber 10 Grouting Pipe is set around side, carries out grouting and reinforcing.The grouting layer 618 should form continuous shielding ring, thickness can 20cm~ 50cm should use physical prospecting or geological radar etc. to monitor the formation effect of grouting layer 618 after construction.
In an embodiment of the invention, it is located at the casing 62 in 61 outside of artificial barrier structure body, should selects Country rock with good heat-conductive characteristic and ion adsorption capacity, such as soft rock or shale etc., and the casing 62 is effective Thickness is no less than 70m, for adsorbing the isotopic ion that a small amount of loss comes out, to realize that underground neutron energy power station occupies the mankind Firmly environment is completely isolated.The vertical range of the artificial barrier structure body 61 apart from ground is not less than 70m.
It should construct in Specific construction, finally bind from outside to inside.According to the steadiness of casing 62, construct respectively Grouting layer 618 and reinforced concrete floor 617, then construct argillic horizon 616 and lead powder concrete layer 615, later by energy production System 2 is placed in the accommodating chamber 614 of artificial barrier structure 61, then, debug energy production system 2, after apply according to this Lead powder concrete layer 615, argillic horizon 616 and the reinforced concrete floor 617 of the roof 613 of worker's work barrier structure body 61, it is complete At sealing.
The anti-nuclein migration barriers 6 have multistage barrier structure, safe, highly practical, and can be effectively real Existing underground neutron energy power station and extraneous energy exchange, effectively prevent the diffusion of underground neutron energy power station entire life cycle Radionuclide With migration, it can be achieved that underground neutron energy power station and human residential environment's is effectively isolated, ensure underground neutron energy power station and the mankind The safety of living environment.
The other end of the main tunnel structure body 101 of 3 chamber 10 located underground of waste heat collection and utilization system, waste heat acquisition profit It is connected respectively with energy production system 2, electricity generation system 4 with system 3.As shown in figure 13, which includes:
Main electricity generation system waste heat acquisition utilizes circuit 31, has the First Heat Exchanger being connected with the electricity generation system 4 311, the First Heat Exchanger 311 is connected with the first hot trap, and the electricity generation system 4 is connected with the energy production system 2;
The acquisition of shielding construction waste heat utilizes circuit 32, has heat exchanger tube 321,322 and of the second heat exchanger being sequentially connected Second hot trap, the heat exchanger tube 321 are arranged in the peripheral side of the energy production system 2.
According to the operation state in underground neutron energy power station, there can be a large amount of waste heat around energy production system 2, simultaneously Steam by electricity generation system 4 will also have higher energy, waste heat collection and utilization system of the invention to pass through main electricity generation system Waste heat acquisition acquires the waste heat that electricity generation system 4 generates using circuit 31, and is acquired by shielding construction waste heat and adopted using circuit 32 Collect the waste heat that energy production system 2 generates, to which the energy in underground neutron energy power station efficiently be utilized, and can electricity to underground neutron The safe operation stood provides safeguard.
Further, which further includes that residual heat of nuclear core acquisition utilizes circuit 33, has phase successively Cooling water tank 331, third heat exchanger 332 and third hot trap even, the cooling water tank 331 are arranged under energy production system 2 Portion.Residual heat of nuclear core acquisition can also be used for the waste heat of the generation of collecting energy generation system 2 using circuit 33.
It follows that the operation state according to underground neutron energy power station, in a feasible embodiment, waste heat acquisition profit The main electricity generation system waste heat acquisition of unlatching may be selected with system and utilize circuit 32 using circuit 31 and the acquisition of shielding construction waste heat, so as to Waste heat during locality descending neutron energy power station to run;In another feasible embodiment, which can Selection is opened residual heat of nuclear core acquisition and is acquired using circuit 32 and main electricity generation system waste heat using circuit 33, the acquisition of shielding construction waste heat Using circuit 31, locality to descend the waste heat during the operation of neutron energy power station more fully hereinafter.
The three waste heats acquisition for being used for the waste heat collection and utilization system in underground neutron energy power station utilizes circuit, that is, heap The acquisition of core waste heat utilizes circuit using circuit 33, the acquisition of shielding construction waste heat using circuit 32 and the acquisition of main electricity generation system waste heat 31, it independently of each other and does not interfere with each other, the waste heat for increasing the present invention acquires the efficiency utilized.
The energy production system 2 in underground neutron energy power station is the core in underground neutron energy power station, is the specific of energy production Unit, the reactor core 211 of the energy production system 2 are the main places of fuel reaction, will generate higher energy, the energy production System 2 is placed in anti-nuclein migration barriers 6 located underground, which has accommodating chamber 614, should Energy production system 2 is located in accommodating chamber 614.Electricity generation system 4 has the steam generator 41 being sequentially connected, steam turbine 42 and hair Motor 43, the steam generator 41 are connected with energy production system 2, are located at the top of accommodating chamber 614, which uses Electric energy is converted in the energy for discharging energy production system 2.
Three waste heats acquisition that the waste heat collection and utilization system for underground neutron energy power station is detailed below utilizes back The structure on road:
The main electricity generation system waste heat acquisition mainly acquires the remaining high-temperature steam of electricity generation system 4 using circuit 31, so as to again It utilizes, there is the First Heat Exchanger 311 being connected with electricity generation system 4, the First Heat Exchanger 311 to be connected with the first hot trap.Wherein, It is connected by the 5th pipeline 44 between the steam generator 41 and steam turbine 42 of electricity generation system 4, which is connected to On 5th pipeline 44, that is, first by the 5th pipeline 44 between the steam generator 41, steam turbine 42 and First Heat Exchanger 311 Tail is connected;It is connected by the 6th pipeline 312 between the First Heat Exchanger 311 and the first hot trap.
In the present invention, electricity generation system 4 realizes the connection with energy production system 2, the steam by steam generator 41 Generator 41 is located at the top of accommodating chamber 614, which realizes the heap with energy production system 2 by built-in pipeline Lead or lead bismuth alloy in core 211 carry out heat exchange, and generate high temperature and high pressure steam, which passes through the 5th first 441 pushing turbine 42 of outlet pipe of pipeline 44 rotates, and then generator 43 is made to produce electricl energy, and realizes the transmission with the external world, Still there is higher temperature by the steam of steam turbine 42, can realize that the heat with the first hot trap is handed over by First Heat Exchanger 311 It changes, subsequently becomes condensed water, steam generator 41 is flowed back into using the water inlet pipe 442 of the 5th pipeline 44.The one of the present invention , can be as needed in embodiment, acceleration pump is set on First Heat Exchanger 311 and the 6th pipeline 312 of the first hot trap, to accelerate Cycle in circuit.The high-temperature water in the 6th pipeline 312 after the heating of First Heat Exchanger 311, the water inlet through the 6th pipeline 312 Heat exchange occurs for pipe 3121 and the first hot trap, energy is gathered in the first hot trap, the later cooling water of heat exchange passes through the 6th The outlet pipe 3122 of pipeline 312, which continues to flow back at First Heat Exchanger 311, to be recycled.
Shielding construction waste heat acquisition utilizes the waste heat of 32 main collecting energy generation system 2 of circuit, by two circuits It is composed in series, the heat exchange between circuit is realized in two circuits by the second heat exchanger 322.Wherein, first circuit is by heat exchanger tube 321, third pipeline 323 and the second heat exchanger 322 composition, pass through third pipeline between heat exchanger tube 321 and the second heat exchanger 322 323 are connected, which is equipped with second circulation and pumps 3233, and second circulation pump 3233 is for controlling first circuit The speed of middle recirculated water realizes the control acquired to waste heat;Second circuit is by the second heat exchanger 322, the 4th pipeline 324 and Two hot traps form, and are connected by the 4th pipeline 324 between second heat exchanger 322 and the second hot trap.In the present invention, the energy The waste heat of generation system 2 is realized by heat exchanger tube 321 and is acquired, and is exchanged heat through second by the outlet pipe of third pipeline 323 3232 Device 322 realizes the heat exchange with second circuit, and cooling water flows back to heat exchanger tube by the water inlet pipe 3231 of third pipeline 323 later 321 recycle, and realize the closure in first circuit.The high-temperature water in second circuit after the heating of the second heat exchanger 322, Heat exchange occurs for water inlet pipe 3242 through the 4th pipeline 324 and the second hot trap, and energy is gathered in the second hot trap, heat exchange with Cooling water afterwards continues to flow back at the second heat exchanger 322 by the outlet pipe 3241 of the 4th pipeline 324 to be recycled.
In the present embodiment, as shown in figure 14, heat exchanger tube 321 includes the circumferential heat exchanger tube 3211 being connected and vertical heat exchange Pipe 3212, the vertical heat exchanger tube 3212 are located at all side-walls of accommodating chamber 614, which is embedded in anti-nucleic and moves It moves in barriers 6.Specifically, the vertical heat exchanger tube 3212 has the vertical water inlet pipe 32121 being connected and vertical outlet pipe 32122, which has circumferential water inlet pipe 32111 and circumferential outlet pipe 32112, the circumferential direction water inlet pipe 32111 It is connected with vertical water inlet pipe 32121, which is connected with vertical outlet pipe 32122.Wherein, vertical outlet pipe 32122 are arranged close to anti-nuclein migration barriers 6, which is arranged close to energy production system 2.In this hair In bright, which is evenly arranged around the peripheral annular of energy production system 2, can increase vertical heat exchanger tube in this way 3212 heat exchange area, farthest to take away the waste heat of energy production system 2, the circumferential direction heat exchanger tube 3211 is in anti-nucleic It migrates and is circumferentially arranged in the lead powder concrete layer of barriers 6, according to heat exchange needs, the circumferential water inlet of the circumferential direction heat exchanger tube 3211 Pipe 32111 and circumferential outlet pipe 32112 can be vertically arranged a ring or polycyclic, not be limited herein.The circumferential direction heat exchanger tube 3211 Circumferential water inlet pipe 32111 and circumferential outlet pipe 32112 pass through the water inlet pipe 3231 of third pipeline 323 and outlet pipe 3232 respectively It is connect with the second heat exchanger 322.
Residual heat of nuclear core acquisition utilizes the waste heat of 33 main collecting energy generation system 2 of circuit, by two circuit in series The heat exchange between circuit is realized in composition, two circuits by third heat exchanger 332.Wherein, first circuit is mainly by being arranged The cooling water tank 331 of 2 lower part of energy production system, the first pipeline 333 and third heat exchanger 332 form, cooling water tank 331 and the It is connected by the first pipeline 333 between three heat exchangers 332, which is equipped with first circulation and pumps 3333, this first is followed Speed of the ring pump 3333 for controlling recirculated water in first circuit realizes the control of the waste heat acquisition to energy production system 2; Second circuit is mainly made of third heat exchanger 332, the second pipeline 334 and third hot trap, the third heat exchanger 332 and third It is connected by the second pipeline 334 between hot trap.In the present invention, cooling water tank 331 is located at the receiving of anti-nuclein migration barriers 6 614 lower part of chamber, the cooling water in first circuit flow through energy production system by the water inlet pipe 3331 of the first pipeline 333 first The heat exchange with the reactor core 211 of energy production system 2 is realized in the lower part of system 2 at cooling water tank 331, passes through the first pipe later The outlet pipe 3332 on road 333 flows back to the heat exchange of third heat exchanger 332 realization and second circuit, and it is lower cold to become temperature But cooling water tank 331 is flowed back by water inlet pipe 3331 after water.High temperature after the heating of third heat exchanger 332 in second circuit Water, the water inlet pipe 3341 through the second pipeline 334 occur heat exchange with third hot trap, energy are gathered in third hot trap, heat is handed over It changes later cooling water and continues to flow back at third heat exchanger 332 by the outlet pipe 3342 of the second pipeline 334 and recycled. Due to the cooling water in cooling water tank 331 itself formed first circuit, first circuit not with where third hot trap Water coke slurry occurs for second circuit, therefore is avoided that the high outflow for putting substance, prevents nuclear leakage.In case of emergency, Ke Yiqi The first circulation pump 3333 in first circuit is moved, accelerates the flow rate of cooling water tank 331 and third heat exchanger 332, improves Heat exchange efficiency reinforces the export ability of 211 decay heat of reactor core, prevents the overheat of reactor core 211 from melting.
In the present invention, first hot trap, the second hot trap and third hot trap can be connected separately with external heating system 37.It should First hot trap, the second hot trap and third hot trap realize the recycling of waste heat by the acquisition of each waste heat using circuit, pass through each time Road needs the heating system 37 of thermal energy to carry out heat exchange with extraneous, and the cooling water after exchange flows back into the first hot trap, the second heat In trap and third hot trap, realization recycles.First hot trap, the second hot trap and third hot trap potentially for heat target, namely The heating system 37, it may include municipal administration implementation such as ground heating system, winter heating system or swimming pool of building etc..
The waste heat collection and utilization system for underground neutron energy power station of the present invention uses three waste heat acquisitions and utilizes back The mode on road realizes acquisition and the recycling of residual heat of nuclear core, barrier structure waste heat and main electricity generation system waste heat respectively, has waste heat Using wide, the advantages that potential Land use systems are more, it is effectively improved the efficiency of energy utilization in underground neutron energy power station, preferably Solves the problems, such as the recycling of 70% waste heat.In addition, residual heat of nuclear core acquisition is utilized using circuit 33 and the acquisition of shielding construction waste heat Circuit 32 can effectively export 211 decay heat of 211 waste heat of reactor core and reactor core, prevent reactor core 211 is excessively thermogenetic from melting heap phenomenon, favorably Safety in underground neutron energy power station.Waste heat collection and utilization system for underground neutron energy power station uses the concatenated side of multiloop Formula carries out waste heat acquisition, waste heat transmission and UTILIZATION OF VESIDUAL HEAT IN, and it is outside by the water loop of heat supply can effectively to evade radioactive element It transmits on boundary.
In one embodiment of the present invention, according to geological conditions and formation conditions, three waste heat acquisitions can be utilized back Road carries out different space layouts;In addition, three waste heat acquisitions can share a hot trap using circuit, that is, the first hot trap, Second hot trap and third hot trap are the same hot trap 34, and in this embodiment, hot trap 34 needs heat by circuit 341 and the external world The heating system 37 of energy carries out heat exchange, which is habitat of three waste heats acquisitions using circuit, convenient for construction and skill Art management reduces whole investment.Alternatively, the first hot trap, the second hot trap described in above-described embodiment can also be used in the present invention The form being provided separately with third hot trap, is not limited herein.According to local conditions, the waste heat of acquisition can be used for difference Purposes.
In addition, also there is ventilation distribution system 8, the ventilation distribution system 8 to be placed in the underground neutron energy power station of the present invention In one of underground chamber 10 branch tunnel structure body 102, which includes electrical corollary apparatus 81 and leads to Wind water feeding and draining device 82 is existing mature technology, does not specifically describe herein;The underground neutron energy power station also has fuel Stocking system 9, the fuel storage system 9 are placed in another branch's tunnel structure body 102 of underground chamber 10.Wherein, exist In the present invention, it is placed in branch's tunnel structure body 102 of fuel storage system 9 and is additionally provided with shield door 103, the shield door 103 For closing branch's tunnel, to realize that fuel storage system 9 is isolated with external.
The underground neutron energy power station of the present invention, neutron source system 1, energy production system 2, waste heat collection and utilization system 3 With electricity generation system 4 is elongated is arranged in underground chamber 10, on the one hand, reduce the excavation span of underground chamber 10, reduce On the other hand construction cost easily descends the blockette management of neutron energy power station.In addition, being equipped with screen in main tunnel structure body 101 Door 103 is covered, which is divided into neutron energy chamber 105 and cogeneration chamber by the shield door 103 106.Wherein, the neutron source system 1 and energy production system 2 in neutron energy chamber 105 for placing underground neutron energy power station;Heat Waste heat collection and utilization system 3 and electricity generation system 4 in electricity supply chamber 106 for placing underground neutron energy power station.The shield door 103 can realize that neutron ray and nucleic are isolated with external.
The underground neutron energy power station of the present invention has the advantages that fuel utilization is high, waste material is few and radioactivity is low, degree of safety is high, And it is distributed in underground, is arranged in stripization, key equipment miniaturization is conducive to carry out distributed construction in the whole nation, realizes me The safety of state's function.Since the fuel rate in underground neutron energy power station is high, exists and current AND ENERGY RESOURCES CONSUMPTION IN CHINA amount 30% is provided May, and its cost of electricity-generating is also relatively low.Therefore, it is optimization China's energy resource structure, the important channel of Environment control problem it One.The fuel ratio tradition nuclear power station in underground neutron energy power station is easily obtained, and using conventional nuclear power waste material as fuel, There is no the defects of fuel poverty.Underground neutron energy power station is arranged and underground, and the anti-nuclein migration barrier provided with multi-turn layer Body realizes underground neutron energy power plant construction, operation, retired and waste disposal integrated setting, reduces whole build and throws Money.
The foregoing is merely several embodiments of the present invention, and those skilled in the art is according to application documents disclosure Various changes or modifications can be carried out without departing from the spirit and scope of the present invention to the embodiment of the present invention.

Claims (30)

1. a kind of underground neutron energy power station, which is characterized in that in the chamber located underground of the underground neutron energy power station comprising:
Neutron source system, is located at one end of the underground chamber, and the neutron source system has the ion for emitting ion Beam tube;
Energy production system, is located at the lower section of the underground chamber, and the energy production system has the reaction for placing reactor core Container is sealedly connected with coupled structure between the reaction vessel and the ion beam tube;
Electricity generation system, is located at the other end of the underground chamber, and the electricity generation system is connected with the energy production system;
Waste heat collection and utilization system, be located at the underground chamber the other end, the waste heat collection and utilization system respectively with institute State energy production system, the electricity generation system is connected.
2. underground neutron energy power station as described in claim 1, which is characterized in that the lower section of the underground chamber is equipped with anti-nucleic Barriers are migrated, the energy production system is located in the anti-nuclein migration barriers.
3. underground neutron energy power station as claimed in claim 2, which is characterized in that the anti-nuclein migration barriers include:
Artificial barrier structure in the underground chamber lower part is set, and the artificial barrier structure has bottom wall, all side walls And roof, it is formed with accommodating chamber between the bottom wall, all side walls and the roof, the energy production system is placed on institute State in accommodating chamber, the bottom wall, all side walls and the roof all have the lead powder concrete layer set gradually from the inside to the outside, Argillic horizon and reinforced concrete floor;
Grouting layer is disposed around the outside of the artificial barrier structure;
Casing, is located at the outside of the grouting layer, and the casing has country rock thickness.
4. underground neutron energy power station as claimed in claim 3, which is characterized in that the bottom wall of the roof and the underground chamber It is connected, the outside difference of the reinforced concrete floor of the outside of the reinforced concrete floor of the bottom wall and all side walls Equipped with the grouting layer.
5. underground neutron energy power station as claimed in claim 3, which is characterized in that the argillic horizon includes ball clay internal layer and glues Native powder outer layer, the ball clay internal layer are spliced to form by multiple ball clays, and the clay powder outer layer is folded in the ball clay Between layer and the reinforced concrete floor.
6. underground neutron energy power station as claimed in claim 3, which is characterized in that the argillic horizon splices shape by multiple ball clays At.
7. underground neutron energy power station as claimed in claim 5, which is characterized in that the ball clay internal layer of the bottom wall includes Multiple torus and the central block being arranged in the middle part of the multiple torus, the torus are spliced by multiple arcs block It is formed.
8. underground neutron energy power station as claimed in claim 6, which is characterized in that the argillic horizon of the bottom wall includes multiple Torus and the central block being arranged in the middle part of the multiple torus, the torus splice shape by multiple arcs block At.
9. underground neutron energy power station as claimed in claim 7 or 8, which is characterized in that the central block is square block; Alternatively, the central block is made of two trapezoidal block splicings.
10. underground neutron energy power station as described in claim 1, which is characterized in that the underground chamber is apart from the vertical of ground Distance is not less than 70m.
11. underground neutron energy power station as described in claim 1, which is characterized in that the coupled structure includes:
Target assembly, with line pipe and the target ontology being connected on the line pipe, the line pipe and the ion beam tube It is connected;
Head cover is sealedly connected on the reaction vessel, and the head cover has at least two lamina tectis mutually spliced, described The connecting hole worn for the line pipe is formed between at least two lamina tectis.
12. underground neutron energy power station as claimed in claim 11, which is characterized in that the head cover has connected structure, described At least two lamina tectis are mutually stitched together by the connected structure.
13. underground neutron energy power station as claimed in claim 12, which is characterized in that the connected structure include multiple fins and Multiple grooves, the fin are inserted into the groove, and the multiple fin and the multiple groove are arranged described at least two On the end face that lamina tecti mutually splices.
14. underground neutron energy power station as claimed in claim 12, which is characterized in that the lamina tecti is two, the head cover Plate is semicircle, and two lamina tecti make-ups form the head cover.
15. underground neutron energy power station as claimed in claim 11, which is characterized in that the outer cover of the line pipe is equipped with bilayer Outer tube, the bilayer outer tube have vacuum chamber.
16. underground neutron energy power station as claimed in claim 15, which is characterized in that the line pipe has been externally wrapped with cooling Pipe, the cooling tube are located between the double-deck outer tube and the line pipe.
17. underground neutron energy power station as claimed in claim 16, which is characterized in that the outside of the cooling tube is equipped with reflection and applies Layer.
18. underground neutron energy power station as claimed in claim 11, which is characterized in that the outside of the energy production system is provide with There are containment, the line pipe to be connected on the containment by fixation steel plate.
19. underground neutron energy power station as claimed in claim 11, which is characterized in that the target ontology is inserted into the energy production In the reactor core of system.
20. underground neutron energy power station as described in claim 1, which is characterized in that the waste heat collection and utilization system includes:
The acquisition of main electricity generation system waste heat utilizes circuit, has a First Heat Exchanger being connected with the electricity generation system, and described first Heat exchanger is connected with the first hot trap;
The acquisition of shielding construction waste heat utilizes circuit, has heat exchanger tube, the second heat exchanger and the second hot trap being sequentially connected, described Heat exchanger tube is arranged in the peripheral side of the energy production system.
21. underground neutron energy power station as claimed in claim 20, which is characterized in that the waste heat collection and utilization system is also wrapped It includes:Residual heat of nuclear core acquisition utilizes circuit, has cooling water tank, third heat exchanger and the third hot trap being sequentially connected, described cold But water tank is arranged in the lower part of the energy production system.
22. underground neutron energy power station as claimed in claim 20, which is characterized in that the energy production system, which is placed on, to be located at In the anti-nuclein migration barriers of underground, there is the anti-nuclein migration barriers accommodating chamber, the electricity generation system to have successively Connected steam generator, steam turbine and generator, the steam generator are connected with the energy production system, are located at institute State the top of accommodating chamber.
23. underground neutron energy power station as claimed in claim 22, which is characterized in that the heat exchanger tube includes the circumferential direction being connected Heat exchanger tube and vertical heat exchanger tube, the vertical heat exchanger tube are located at all side-walls of the accommodating chamber, and the circumferential direction heat exchanger tube is embedded In the anti-nuclein migration barriers.
24. underground neutron energy power station as claimed in claim 23, which is characterized in that the vertical heat exchanger tube, which has, to be connected Vertical water inlet pipe and vertical outlet pipe, the circumferential direction heat exchanger tube have circumferential water inlet pipe and circumferential outlet pipe, the circumferential water inlet Pipe is connected with the vertical water inlet pipe, and the circumferential direction outlet pipe is connected with the vertical outlet pipe.
25. underground neutron energy power station as claimed in claim 23, which is characterized in that the vertical outlet pipe is close to the anti-core Element migration barriers setting, the vertical water inlet pipe are arranged close to the energy production system.
26. underground neutron energy power station as claimed in claim 21, which is characterized in that the cooling water tank exchanges heat with the third It is connected by the first pipeline between device, is connected by the second pipeline between the third heat exchanger and the third hot trap, it is described First pipeline is equipped with to be pumped for the first circulation of control loop water speed.
27. underground neutron energy power station as claimed in claim 20, which is characterized in that the heat exchanger tube and second heat exchanger Between be connected by third pipeline, be connected by the 4th pipeline between second heat exchanger and second hot trap, described the Three pipelines are equipped with to be pumped for the second circulation of control loop water speed.
28. underground neutron energy power station as claimed in claim 22, which is characterized in that the steam generator and the steam turbine Between by the 5th pipeline be connected, the First Heat Exchanger is connected on the 5th pipeline, the First Heat Exchanger with it is described It is connected by the 6th pipeline between first hot trap.
29. underground neutron energy power station as claimed in claim 21, which is characterized in that first hot trap, second hot trap It is connected separately with external heating system with the third hot trap.
30. underground neutron energy power station as described in claim 1, which is characterized in that the neutron source system includes being sequentially connected Ion source, accelerator and the ion beam tube.
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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019184928A1 (en) * 2018-03-29 2019-10-03 何满潮 Nuclide-migration-prevention barrier for underground neutron energy power station and construction method therefor
WO2019184932A1 (en) * 2018-03-29 2019-10-03 何满潮 Underground neutron-energy power station

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FI20167018L (en) * 2016-12-30 2018-07-01 Brown David Method and apparatus for producing energy from metal alloys

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20030152186A1 (en) * 2002-01-28 2003-08-14 Jurczyk Brian E. Gas-target neutron generation and applications
US20080232533A1 (en) * 2006-02-15 2008-09-25 Anatoly Blanovsky High flux sub-critical reactor for nuclear waste transmulation
CN101916607A (en) * 2010-07-28 2010-12-15 北京大学 Small neutron source adopting windowless gas target
CN104167226A (en) * 2014-09-05 2014-11-26 中国科学院合肥物质科学研究院 Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test
CN105407621A (en) * 2015-11-13 2016-03-16 兰州大学 Compact type D-D neutron generator
CN106531229A (en) * 2016-12-29 2017-03-22 中国科学院合肥物质科学研究院 Novel ring-cavity multifunctional nuclear system
CN106683737A (en) * 2017-02-14 2017-05-17 中国科学院合肥物质科学研究院 Neutron source with gas-state target
CN208570131U (en) * 2018-03-29 2019-03-01 何满潮 Underground neutron energy power station

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4851183A (en) * 1988-05-17 1989-07-25 The United States Of America As Represented By The United States Department Of Energy Underground nuclear power station using self-regulating heat-pipe controlled reactors
JP2003255072A (en) * 2002-03-06 2003-09-10 Shinichi Yokosuka Construction with safety taken into consideration in nuclear power plant
US8971474B2 (en) * 2006-11-28 2015-03-03 Terrapower, Llc Automated nuclear power reactor for long-term operation
CN106531265B (en) * 2016-10-27 2018-07-03 长江勘测规划设计研究有限责任公司 A kind of fully buried layout design method of underground nuclear power station main building group
CN108417283B (en) * 2018-03-29 2023-10-31 何满潮 Underground neutron energy power station

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20030152186A1 (en) * 2002-01-28 2003-08-14 Jurczyk Brian E. Gas-target neutron generation and applications
US20080232533A1 (en) * 2006-02-15 2008-09-25 Anatoly Blanovsky High flux sub-critical reactor for nuclear waste transmulation
CN101916607A (en) * 2010-07-28 2010-12-15 北京大学 Small neutron source adopting windowless gas target
CN104167226A (en) * 2014-09-05 2014-11-26 中国科学院合肥物质科学研究院 Liquid metal cooling reactor experimental system capable of realizing critical and subcritical running test
CN105407621A (en) * 2015-11-13 2016-03-16 兰州大学 Compact type D-D neutron generator
CN106531229A (en) * 2016-12-29 2017-03-22 中国科学院合肥物质科学研究院 Novel ring-cavity multifunctional nuclear system
CN106683737A (en) * 2017-02-14 2017-05-17 中国科学院合肥物质科学研究院 Neutron source with gas-state target
CN208570131U (en) * 2018-03-29 2019-03-01 何满潮 Underground neutron energy power station

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
吴宜灿: "Development of high intensity D–T fusion neutron generator HINEG", INTERNATIONAL JOURNAL OF ENERGY RESEARCH, vol. 42, pages 68 - 72, XP071644466, DOI: 10.1002/er.3572 *
吴宜灿等: "强流氘氚聚变中子源HINEG设计", 第二届中国氚科学与技术学术交流会论文集, pages 173 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2019184928A1 (en) * 2018-03-29 2019-10-03 何满潮 Nuclide-migration-prevention barrier for underground neutron energy power station and construction method therefor
WO2019184932A1 (en) * 2018-03-29 2019-10-03 何满潮 Underground neutron-energy power station

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