CN105976873A - Internal part cooling power generation system for future tokamak fusion reactor - Google Patents

Internal part cooling power generation system for future tokamak fusion reactor Download PDF

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Publication number
CN105976873A
CN105976873A CN201610116474.1A CN201610116474A CN105976873A CN 105976873 A CN105976873 A CN 105976873A CN 201610116474 A CN201610116474 A CN 201610116474A CN 105976873 A CN105976873 A CN 105976873A
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heat exchanger
diaphragm valve
coolant
cooling
major loop
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CN201610116474.1A
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CN105976873B (en
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卯鑫
陆坤
宋云涛
彭学兵
雷明准
李阳
钱新元
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Institute of Plasma Physics of CAS
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Institute of Plasma Physics of CAS
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/05Thermonuclear fusion reactors with magnetic or electric plasma confinement
    • G21B1/057Tokamaks
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/11Details
    • 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

Abstract

The invention provides an internal part cooling power generation system for a future tokamak fusion reactor. The system comprises a divertor cooling circuit, a cladding cooling circuit and a main cooling circuit. The system is characterized in that the divertor cooling circuit comprises a first heat exchanger, a pump and a divertor; a coolant is inflated by the pump from one side of the first heat exchanger, flows into the divertor, and flows back to the first heat exchanger from the other side of the divertor; the cladding cooling circuit comprises a first main circuit, a first auxiliary circuit and a supplemental coolant circuit; and the main cooling circuit comprises a second main circuit and a second auxiliary circuit. According to the invention, on the premise that a tokamak device can continuously stably operate, cooling and power generation are integrated, and the system has the advantages of stability, safety, reliability and high efficiency.

Description

A kind of following Tokamak Fusion Reactor internal part cooling electricity generation system
Technical field
The present invention relates to nuclear energy technology application, particularly relate to a kind of following Tokamak Fusion Reactor internal part cooling electricity generation system, i.e. in the case of magnetic confinement nuclear fusion device continuous service, the energy utilizing deuterium tritium fusion to discharge cools down its internal part divertor and covering while generating electricity.
Background technology
At present, the fossil energy reserves of the earth are limited and pollute air, and the renewable sources of energy (wind energy, solar energy, tide energy) are because of not enough by all its utilization rates that limits, and whole world every country all suffers from the problems such as energy scarcity and environmental pollution.Therefore, people increasingly pay close attention to the development of nuclear power technology.Nuclear power station is that the energy utilizing nuclear fission or nuclear fusion reaction release is to produce the power plant of electric energy.Nuclear fission power station mainly uses radioelement such as uranium and caesium etc. as fuel, and its product is the most buried but environment can produce certain pollution, simultaneously resource-constrained on the radioelement earth, and health also can be worked the mischief by its radiation produced.Nuclear fusion energy is cleanliness without any pollution and the unlimited energy of resource, although also do not have nuclear fusion power plants on our times, but the feasibility of nuclear fusion energy generating is verified on tokamak magnetic confinement nuclear fusion device.The tokamak device all establishing this country of many countries, such as China EAST, Korea S KSTAR, ITER etc. is built in international cooperation.
Research final purpose about tokamak device is to utilize nuclear fusion energy to generate electricity, but reality is, ensure that deuterium tritium is under conditions of the internal sustained response i.e. tokamak device stable state continuous service of tokamak device, can bear the particle flux from central plasma and hot-fluid as it directly facing internal part divertor and the covering of plasma area, the power that its first wall surface bears reaches m. gigawatt (GW) magnitude.It is contemplated that, the heat flow density of cladding surface is up to several megawatts every square metre, and divertor is up to ten megawatts every square metre in the face of plasma unit surface.The biggest energy, remove it without effective cooling system, the temperature on covering and divertor can be made to rise to the unaffordable height of material, so that affecting the operation of device, simultaneously, in order to these cooled fusion energies removed are converted into electric energy, to solve the energy shortage problem that society highlights day by day, and then establish the following Tokamak Fusion Reactor internal part cooling electricity generation system of the present invention.
Summary of the invention
The object of the invention is contemplated to make up the defect of prior art, it is provided that a kind of following Tokamak Fusion Reactor internal part cooling electricity generation system.
The present invention is achieved by the following technical solutions:
A kind of following Tokamak Fusion Reactor internal part cooling electricity generation system, include divertor cooling circuit, covering cooling circuit and main cooling circuit, it is characterized in that: described divertor cooling circuit includes heat exchanger one, pump and divertor, coolant flows into divertor after pump pressurizes from the side of heat exchanger one, heat exchanger one is flowed back to again from the opposite side of divertor, described covering cooling circuit includes major loop one, subsidiary loop one and supplementary coolant circuit, and described main cooling circuit includes major loop two and subsidiary loop two.
Described major loop one includes the covering in steam generator, primary coolant pump and tokamak device, close diaphragm valve one, two, coolant flow out from steam generator through primary coolant pump cooling pressurization laggard enter covering in tokamak device, flow back to steam generator from the opposite side of covering again;Described subsidiary loop one is the most at regular intervals, when in major loop, coolant needs detritiation and cooling, open diaphragm valve one, two, the coolant flowed out from described steam generator is divided into two parts, being partly into primary coolant pump and participate in major loop one circulation, another part enters to participate in major loop one circulation in tokamak device after covering through diaphragm valve one, heat exchanger two, cooler, cooling detritiation system, demineralizer one, volume control tank, feed pump one, regenerative heat exchanger and diaphragm valve are second-rate successively;Described supplementary coolant circuit is when coolant content deficiency during major loop is anticipated, and opens diaphragm valve three, and the coolant in reserving liquid tank after diaphragm valve three, supercharger pressurization, enters major loop one successively.
Described major loop two is for closing diaphragm valve seven, open diaphragm valve four, five, six, eight and gate valve one, two, three, cooling water pump one draws water from condenser, after sequentially passing through filter, demineralizer two, cooling water pump two, heat exchanger one, storage tank, deaerator, feed pump two, heat exchanger two, steam generator, gate valve one, diaphragm valve five, condensing turbine one, heat exchanger three, gate valve two, diaphragm valve six, condensing turbine two, gate valve three, diaphragm valve eight, condensing turbine three, finally return to condenser;Described subsidiary loop two is for closing diaphragm valve seven, open diaphragm valve four, five, six, eight and gate valve one, two, three, the steam of steam generator is divided into two parts, a part participates in major loop two and circulates, another part, successively through diaphragm valve four, heat exchanger three, air relief valve two, heat exchanger two, air relief valve one, participates in major loop two and circulates after entering deaerator;Drawn steam successively through heat exchanger three, air relief valve three, heat exchanger two, air relief valve one by the intergrade of condensing turbine one, participate in major loop two after entering deaerator and circulate;Being drawn two pipelines by the intergrade of condensing turbine two, the steam in two pipelines, successively after heat exchanger two, air relief valve one, participates in major loop two and circulates after entering deaerator;The steam flowed out by condensing turbine two is divided into two parts, a part flows to gate valve three, and another part flows to the hydraulic turbine and storage tank, flows to the steam of the hydraulic turbine after the hydraulic turbine, flow back to described condenser, and the steam flowing to storage tank is to participate in major loop two circulation;When some breaks down in condensing turbine one, two, three, close diaphragm valve four and gate valve one, open diaphragm valve seven, steam generator the steam flowed out flows to condenser after diaphragm valve seven, the most directly cools down.
Described divertor cooling circuit, covering cooling circuit and main cooling circuit is common acting on and separate, to ensure internal part i.e. covering and the divertor of the tokamak magnetic confinement nuclear fusion device of the following stable state continuous service of cooling, utilize condensing turbine one, two, three is generating by the thermal energy in coolant simultaneously.
The invention have the advantage that the present invention is in the case of tokamak device ensure that stable state continuous service, it is achieved that cooling and generating integrated design, there is the advantages such as stable, safe, reliable, efficient.
Accompanying drawing explanation
Fig. 1 is the structural representation of the present invention.
Detailed description of the invention
As shown in Figure 1, a kind of following Tokamak Fusion Reactor internal part cooling electricity generation system, include divertor cooling circuit, covering cooling circuit and main cooling circuit, it is characterized in that: described divertor cooling circuit includes heat exchanger 1, pump 39 and divertor 40, coolant flows into divertor 40 after pump 39 pressurizes from the side of heat exchanger 1, opposite side from divertor 40 flows back to heat exchanger 1 again, described covering cooling circuit includes major loop one, subsidiary loop one and supplementary coolant circuit, described main cooling circuit includes major loop two and subsidiary loop two.
Described major loop one includes the covering 42 in steam generator 23, primary coolant pump 19 and tokamak device, close diaphragm valve one 17,2 18, coolant flow out from steam generator 23 through primary coolant pump 19 cooling pressurization laggard enter covering 42 in tokamak device, the opposite side from covering 42 flows back to steam generator 23 again;Described subsidiary loop one is the most at regular intervals, when in major loop, coolant needs detritiation and cooling, open diaphragm valve 1, 2 18, the coolant flowed out from described steam generator 23 is divided into two parts, it is partly into primary coolant pump 19 and participates in major loop one circulation, another part is successively through diaphragm valve 1, heat exchanger 2 11, cooler 15, cooling detritiation system 43, demineralizer 1, volume control tank 13, feed pump 1, regenerative heat exchanger 16 and diaphragm valve 2 18 inflow tokamak device participate in major loop one after covering 42 circulate;Described supplementary coolant circuit is when coolant content deficiency during major loop is anticipated, and opens diaphragm valve 3 22, and the coolant in reserving liquid tank 41 after diaphragm valve 3 23, supercharger 20 pressurization, enters major loop one successively.
Described major loop two is for closing diaphragm valve 7 32, open diaphragm valve 4 24, 5 27, 6 30, 8 34 and gate valve 1, 2 29, 3 33, cooling water pump 1 draws water from condenser 38, sequentially pass through filter 2, demineralizer 23, cooling water pump 24, heat exchanger 1, storage tank 6, deaerator 7, feed pump 28, heat exchanger 2 11, steam generator 23, gate valve 1, diaphragm valve 5 27, condensing turbine 1, heat exchanger 3 25, gate valve 2 29, diaphragm valve 6 30, condensing turbine 2 31, gate valve 3 33, diaphragm valve 8 34, after condensing turbine 3 35, finally return to condenser 38;Described subsidiary loop two is for closing diaphragm valve 7 32, open diaphragm valve 4 24,5 27,6 30,8 34 and gate valve one 26,2 29,3 33, the steam of steam generator 23 is divided into two parts, a part participates in major loop two and circulates, another part, successively through diaphragm valve 4 24, heat exchanger 3 25, air relief valve 2 36, heat exchanger 2 11, air relief valve 1, participates in major loop two and circulates after entering deaerator 7;Drawn steam successively through heat exchanger 3 25, air relief valve 3 37, heat exchanger 2 11, air relief valve 1 by the intergrade of condensing turbine 1, participate in major loop two after entering deaerator 7 and circulate;Being drawn two pipelines by the intergrade of condensing turbine 2 31, the steam in two pipelines, successively after heat exchanger 2 11, air relief valve 1, participates in major loop two and circulates after entering deaerator 7;The steam flowed out by condensing turbine 2 31 is divided into two parts, a part flows to gate valve 3 33, and another part flows to the hydraulic turbine 9 and storage tank 6, flows to the steam of the hydraulic turbine 9 after the hydraulic turbine 9, flow back to described condenser 38, and the steam flowing to storage tank 6 is to participate in major loop two circulation;When in condensing turbine one 28,2 31,3 35, some breaks down, close diaphragm valve 4 24 and gate valve 1, open diaphragm valve 7 32, steam generator 23 steam flowed out flows to condenser 38 after diaphragm valve 7 32, directly cools down in condenser 38.
Described divertor cooling circuit, covering cooling circuit and main cooling circuit is common acting on and separate, to ensure internal part i.e. covering and the divertor of the tokamak magnetic confinement nuclear fusion device of the following stable state continuous service of cooling, utilize condensing turbine one 28,2 31,3 35 is generating by the thermal energy in coolant simultaneously.
In described covering cooling circuit, the effect of each components and parts is as follows:
The effect of coolant in major loop and subsidiary loop: (a) absorbs and take covering heat out of and i.e. cool down covering;B () completes heat exchange with the cooling water carrying out autonomous cooling circuit in steam generator 23.
The effect of steam generator 23: make the cooling water of relative low temperature in main cooling circuit carry out heat exchange with the coolant of relatively-high temperature in covering loop, cool down water after heat exchange to become steam and enter main cooling circuit, and make the coolant of relative low temperature after heat exchange enter covering loop.
The effect of subsidiary loop: when the tritium level in main coolant loop and temperature can not meet the requirement of cooling covering, major loop is carried out detritiation cooling.
The effect of diaphragm valve one 17,2 18,3 22: block stream and regulate uninterrupted.
The effect of regenerative heat exchanger 16: even if the coolant temperature that the coolant flowed through in 16 two pipelines of hot recycling exchanger carries out heat exchange inflow covering 42 meets requirement.
The effect of cooler 15: cooling coolant after regenerative heat exchanger 16 heat exchange.
The effect of feed pump 1: extract coolant from Volume controller 13 and coolant is pressurizeed.
The effect of demineralizer 1: the coolant flowed through is carried out desalting processing.
The effect of Volume controller 13: store the coolant of a constant volume and encircle coolant to feed pump 1.
The effect of main coolant circulation pump 19: coolant in major loop is carried out pressurization cooling.
The effect of supercharger 20: supplement the coolant of certain pressure for major loop.
In described main cooling circuit, the effect of each components and parts is as follows:
The effect of cooling water pump 1: extraction cools down water and the cooling water flowed through carries out pressurization and cools down from condenser 38.
The effect of filter 2: filter the impurity flowed through in cooling water.
The effect of demineralizer 23: the cooling water flowed through is carried out desalting processing.
The effect of cooling water pump 24: extraction cools down water and the cooling water flowed through carries out pressurization and cools down from demineralizer 23.
The effect of heat exchanger 1: make the high temperature coolant coming from divertor loop and the low-temperature cooling water coming from cooling water pump 24 carry out heat exchange, and the coolant of relative low temperature flows back to divertor loop after making heat exchange, make the cooling current direction storage tank 6 of relatively-high temperature simultaneously.
The effect of storage tank 6: receive the steam of low-temp low-pressure and store cooling water.
The effect of deaerator 7: remove and flow through the gas dissolved in cooling water, particularly oxygen.
The effect of feed pump 28: extraction cools down water and pressurizes cooling water from deaerator 7.
The effect of the hydraulic turbine 9: utilize the steam acting of the relative low temperature low pressure flowed into provide power for feed pump 8 and discharged by the steam after acting.
The effect of air relief valve one 10,2 36,3 37: to the water vapour decompression flowed through.
The effect of heat exchanger 2 11: make the cooling current direction steam generator 23 of the relatively-high temperature after carrying out heat exchange from the cooling water of feed pump 28 relative low temperature with the steam from subsidiary loop relatively-high temperature and make heat exchange, and make the water vapor stream of relative low temperature to air relief valve 1.
The effect of steam generator 23: make the cooling water of relative low temperature in main cooling circuit carry out heat exchange with the coolant of relatively-high temperature in covering loop, cool down water after heat exchange to become steam and enter main cooling circuit, and make the coolant of relative low temperature after heat exchange enter covering loop.
The effect of diaphragm valve 24,27,30,32,34: block stream and regulate uninterrupted.
The effect of gate valve 26,29,33: switch (standard-sized sheet, fully closed).
The effect of condensing turbine 28: this steam turbine is high-pressure turbine coaxial with condensing turbine 31, utilizes the high temperature and high pressure steam acting generating cooling down high-temperature high steam flowed into;The intergrade utilizing self provides auxiliary heat for heat exchanger 25;The relative medium temperature and medium pressure steam that its end is discharged provides power for condensing turbine 31.
The effect of heat exchanger 25: make the steam from diaphragm valve 24 High Temperature High Pressure, the steam from condensing turbine 28 intergrade relatively-high temperature high pressure and the steam from condensing turbine 28 end relative low temperature low pressure carry out heat exchange, and the steam after each self-loop discharges heat exchange.
The effect of condensing turbine 31: this steam turbine is middle-pressure steam turbine, utilizes the steam acting generating of the relative medium temperature and medium pressure of automatic heat-exchanger 25 and cools down medium temperature and medium pressure steam;The intergrade utilizing self provides auxiliary heat for heat exchanger 11;The relative low temperature low-pressure steam that its end is discharged provides power for condensing turbine 35 and the hydraulic turbine 9 and provides auxiliary heat for storage tank 6.
The effect of condensing turbine 35: this steam turbine is low-pressure turbine, utilizes the steam acting from condensing turbine 31 relative low temperature low pressure generate electricity and cool down low temperature and low pressure steam, and its end pipeline is connected with condenser 38.
The effect of condenser 38: cooling from condensing turbine 35, the hydraulic turbine 9 and the steam of diaphragm valve 32 and is supplied water to cooling water pump 1.
Under the common effect of divertor cooling circuit, covering cooling circuit and main cooling circuit, tentatively achieve the cooling of the internal part (covering and divertor) of the tokamak magnetic confinement nuclear fusion device of following stable state continuous service and utilize the energy in coolant to generate electricity.
Although detailed description of the invention illustrative to the present invention is described above; so that those skilled in the art understand the present invention; and it should also be apparent that; the invention is not restricted to the scope of detailed description of the invention; from the point of view of those skilled in the art; as long as various changes limit and in the spirit and scope of the present invention that determine, these changes are apparent from, and all utilize the innovation and creation of present inventive concept all at the row of protection in appended claim.

Claims (4)

1. a following Tokamak Fusion Reactor internal part cooling electricity generation system, include divertor cooling circuit, covering cooling circuit and main cooling circuit, it is characterized in that: described divertor cooling circuit includes heat exchanger one, pump and divertor, coolant flows into divertor after pump pressurizes from the side of heat exchanger one, heat exchanger one is flowed back to again from the opposite side of divertor, described covering cooling circuit includes major loop one, subsidiary loop one and supplementary coolant circuit, and described main cooling circuit includes major loop two and subsidiary loop two.
A kind of following Tokamak Fusion Reactor internal part cooling electricity generation system the most according to claim 1, it is characterized in that: described major loop one includes the covering in steam generator, primary coolant pump and tokamak device, coolant flow out from steam generator through primary coolant pump cooling pressurization laggard enter covering in tokamak device, flow back to steam generator from the opposite side of covering again;Described subsidiary loop one is that the coolant flowed out from described steam generator is divided into two parts, being partly into primary coolant pump and participate in major loop one circulation, another part enters to participate in major loop one circulation in tokamak device after covering through diaphragm valve one, heat exchanger two, cooler, cooling detritiation system, demineralizer one, volume control tank, feed pump one, regenerative heat exchanger and diaphragm valve are second-rate successively;Described supplementary coolant circuit is when coolant content deficiency during major loop is anticipated, and opens diaphragm valve three, and the coolant in reserving liquid tank after diaphragm valve three, supercharger pressurization, enters major loop one successively.
A kind of following Tokamak Fusion Reactor internal part cooling electricity generation system the most according to claim 2, it is characterized in that: described major loop two is for closing diaphragm valve seven, open diaphragm valve four, five, six, eight and gate valve one, two, three, cooling water pump one draws water from condenser, sequentially pass through filter, demineralizer two, cooling water pump two, heat exchanger one, storage tank, deaerator, feed pump two, heat exchanger two, steam generator, gate valve one, diaphragm valve five, condensing turbine one, heat exchanger three, gate valve two, diaphragm valve six, condensing turbine two, gate valve three, diaphragm valve eight, after condensing turbine three, finally return to condenser;Described subsidiary loop two is for closing diaphragm valve seven, open diaphragm valve four, five, six, eight and gate valve one, two, three, the steam of steam generator is divided into two parts, a part participates in major loop two and circulates, another part, successively through diaphragm valve four, heat exchanger three, air relief valve two, heat exchanger two, air relief valve one, participates in major loop two and circulates after entering deaerator;Drawn steam successively through heat exchanger three, air relief valve three, heat exchanger two, air relief valve one by the intergrade of condensing turbine one, participate in major loop two after entering deaerator and circulate;Being drawn two pipelines by the intergrade of condensing turbine two, the steam in two pipelines, successively after heat exchanger two, air relief valve one, participates in major loop two and circulates after entering deaerator;The steam flowed out by condensing turbine two is divided into two parts, a part flows to gate valve three, and another part flows to the hydraulic turbine and storage tank, flows to the steam of the hydraulic turbine after the hydraulic turbine, flow back to described condenser, and the steam flowing to storage tank is to participate in major loop two circulation;When some breaks down in condensing turbine one, two, three, close diaphragm valve four and gate valve one, open diaphragm valve seven, steam generator the steam flowed out flows to condenser after diaphragm valve seven, the most directly cools down.
A kind of following Tokamak Fusion Reactor internal part cooling electricity generation system the most according to claim 3, it is characterized in that: described divertor cooling circuit, covering cooling circuit and main cooling circuit is common acting on and separate, utilize condensing turbine one, two, three is generating by the thermal energy in coolant simultaneously.
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Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108335759A (en) * 2018-02-06 2018-07-27 华中科技大学 The cooling system for tokamak device divertor based on evaporation cooling principle
CN109599191A (en) * 2018-10-16 2019-04-09 中国科学院合肥物质科学研究院 A kind of cooling loop system based on Superconducting tokamak device
CN110739086A (en) * 2019-10-22 2020-01-31 中国科学院合肥物质科学研究院 auxiliary loop for Tokamak fusion device cooling power generation system
CN110767323A (en) * 2019-10-14 2020-02-07 中国科学院合肥物质科学研究院 Intermediate heat exchange system for nuclear fusion device
CN113851231A (en) * 2021-08-25 2021-12-28 中国科学院合肥物质科学研究院 Method and device for improving tritium value-added rate of fusion reactor
CN115235134A (en) * 2022-09-22 2022-10-25 中国科学院合肥物质科学研究院 Supercritical carbon dioxide circulating system for fusion reactor

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20110170649A1 (en) * 2010-01-11 2011-07-14 Kotschenreuther Michael T Magnetic confinement device with aluminum or aluminum-alloy magnets
CN103578579A (en) * 2013-10-16 2014-02-12 中国核电工程有限公司 Advanced fusion-fission subcritical energy reactor core
CN104051028A (en) * 2014-06-05 2014-09-17 中国科学院等离子体物理研究所 Passive feedback structure suitable for controlling plasmas of future fusion reactor rapidly
CN204087826U (en) * 2014-08-21 2015-01-07 中国工程物理研究院核物理与化学研究所 A kind of subcritical covering refuelling system

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20110170649A1 (en) * 2010-01-11 2011-07-14 Kotschenreuther Michael T Magnetic confinement device with aluminum or aluminum-alloy magnets
CN103578579A (en) * 2013-10-16 2014-02-12 中国核电工程有限公司 Advanced fusion-fission subcritical energy reactor core
CN104051028A (en) * 2014-06-05 2014-09-17 中国科学院等离子体物理研究所 Passive feedback structure suitable for controlling plasmas of future fusion reactor rapidly
CN204087826U (en) * 2014-08-21 2015-01-07 中国工程物理研究院核物理与化学研究所 A kind of subcritical covering refuelling system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
吴宜灿等: "聚变发电反应堆概念设计研究"", 《核科学与工程》 *

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108335759A (en) * 2018-02-06 2018-07-27 华中科技大学 The cooling system for tokamak device divertor based on evaporation cooling principle
CN109599191A (en) * 2018-10-16 2019-04-09 中国科学院合肥物质科学研究院 A kind of cooling loop system based on Superconducting tokamak device
CN110767323A (en) * 2019-10-14 2020-02-07 中国科学院合肥物质科学研究院 Intermediate heat exchange system for nuclear fusion device
CN110739086A (en) * 2019-10-22 2020-01-31 中国科学院合肥物质科学研究院 auxiliary loop for Tokamak fusion device cooling power generation system
CN113851231A (en) * 2021-08-25 2021-12-28 中国科学院合肥物质科学研究院 Method and device for improving tritium value-added rate of fusion reactor
CN115235134A (en) * 2022-09-22 2022-10-25 中国科学院合肥物质科学研究院 Supercritical carbon dioxide circulating system for fusion reactor
CN115235134B (en) * 2022-09-22 2022-12-20 中国科学院合肥物质科学研究院 Supercritical carbon dioxide circulation system for fusion reactor

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