CN110739086A - auxiliary loop for Tokamak fusion device cooling power generation system - Google Patents
auxiliary loop for Tokamak fusion device cooling power generation system Download PDFInfo
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- CN110739086A CN110739086A CN201911003036.4A CN201911003036A CN110739086A CN 110739086 A CN110739086 A CN 110739086A CN 201911003036 A CN201911003036 A CN 201911003036A CN 110739086 A CN110739086 A CN 110739086A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/05—Thermonuclear fusion reactors with magnetic or electric plasma confinement
- G21B1/057—Tokamaks
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
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Abstract
The invention discloses auxiliary loops suitable for a Tokamak fusion device cooling power generation system, wherein a main loop (also called a loop) comprises a cladding and a divertor cooling loop, coolant in the main loop takes away a large amount of nuclear heat generated by the fusion device and carries out power generation through two loops, and the auxiliary loop comprises a vacuum chamber cooling loop, a waste heat discharge system, a pressure control and overpressure protection system and a volume control and purification system.
Description
Technical Field
The invention relates to the field of nuclear energy technology application, in particular to an auxiliary loop for a Tokamak fusion device cooling power generation system.
Background
Tokamak fusion device , which is the most productive means for studying magnetic confinement fusion energy, is mainly composed of cladding, divertor, vacuum chamber, cold screen, dewar and magnet.
The present study on the Tokamak fusion device cooling power generation system is that the cladding and divertor are cooled by coolant and the energy is removed, so the Tokamak fusion device cooling power generation system is a 'main loop', in addition, the heat energy replaced by the main loop is converted into electric energy by components such as heat exchangers, condensers and steam turbines, so the 'two-loop' patent is granted, see the publication No. CN 105976873A: future Tokamak fusion device internal component cooling power generation system, the problem of energy discharge of a vacuum chamber due to the huge energy release when fusion occurs and the operation characteristics of the Tokamak fusion device, the problem of energy collection in the main loop after the device is stopped, the problem of pressure control and overpressure protection and volume control and purification in the main loop during the device operation, the above patent does not describe, however, the problems are the key points for influencing the normal operation of two loops.
Disclosure of Invention
The purpose of the invention is to make up for the existing technical defects, therefore, auxiliary loops for a Tokamak fusion device cooling power generation system, namely a vacuum chamber loop, a waste heat discharge system, a pressure control and overpressure protection system and a volume control and purification system, solve the problems and simultaneously meet the requirements of steady-state operation of fusion device cooling power generation, and have the advantages of safety, stability, reliability and the like.
The auxiliary loop comprises a vacuum chamber cooling loop, a waste heat discharge system, a pressure control and overpressure protection system and a volume control and purification system;
the vacuum chamber cooling loop exchanges energy with the secondary loop through a second heat exchanger, the waste heat discharge system is connected with the main loop through an manual isolation valve, the pressure control and overpressure protection system is connected with the main loop through a tenth gate valve, and the volume control and purification system is connected with the main loop through a fourth diaphragm valve;
the coolant water of the main loop flows through the fusion device cladding module to take away a large amount of nuclear heat generated by the fusion device, and the taken energy is used for generating electricity through the two loops; the auxiliary loop provides support for the main loop and the secondary loop, and safe and stable operation of the main loop and the secondary loop is ensured.
The vacuum chamber cooling loop comprises a coolant pump second heat exchanger and a plurality of gate valves; the heat generated by the heat exchanger is exchanged with the feed water on the outlet side of the pump of the second loop through the second heat exchanger to preheat the feed water of the second loop.
The fusion device comprises a fusion device, a residual heat discharging system and a manual isolating valve , wherein the fusion device comprises a fusion device body, a residual heat discharging system and a manual isolating valve , the fusion device body is connected with a th equipment cooling water system, the residual heat discharging system is started to take residual heat in a fusion device cladding when the fusion device is stopped, heat generated by nuclear reaction in the fusion device body is not completely taken away, the residual heat discharging system is started to take away the residual heat, the coolant is started to be discharged by the manual isolating valve , the coolant is driven by the residual heat discharging pump to flow through a check valve and enter a heat exchanger for cooling, the th equipment cooling water system is connected with the heat exchanger and exchanges energy with the coolant, and when the temperature and the pressure meet the input requirements of the coolant in a cold pipe section, the second diaphragm valve.
The pressure control and overpressure protection system is used for adjusting dynamic pressure value fluctuation in normal operation of a main loop, performing pressure relief protection on the main loop system when a serious accident occurs, and ensuring safety of parts of the main loop system, and comprises a voltage stabilizer and a pressure relief box, wherein a coolant is controlled by a tenth gate valve through a heat pipe section of the main loop, and reaches the voltage stabilizer through the tenth gate valve after impurities are filtered by a filter 06, sensors for detecting water level, steam temperature, water temperature and pressure are arranged in the pressure control and overpressure protection system for detection, when the fusion device has a serious accident, the pressure is rapidly increased, emergency pressure relief can be performed through a second safety valve at the top of the voltage stabilizer, and safety protection is performed on the main loop.
The pressure stabilizer comprises a pressure stabilizer, a pressure release tank, a cooling water tank, an electric heater, a cooling agent inlet pipe, a main loop, a main spray pipe, a main spray diaphragm valve, a fourth manual isolation valve, a pressure release diaphragm valve, a fourteenth manual isolation valve, a cooling agent outlet pipe, a cooling agent discharge tank, a fourteenth manual isolation valve, a thirteenth manual isolation valve, a fourteenth manual isolation valve, a pressure release valve, a mixture tank, a fourteenth hydrogen discharge tank, a fourteenth manual release valve, a fourteenth manual isolation valve, a pressure release valve, a fourteenth manual release valve, a pressure release valve, a fourteenth hydrogen release valve, a pressure relief valve, a.
The volume control and purification system is used for adjusting the volume fluctuation caused by the temperature change of the coolant in the main loop and purifying the coolant, and the volume control is used for absorbing the volume change of the coolant of the main loop which cannot be absorbed by the voltage stabilizer so that the water level of the voltage stabilizer fluctuates within a safety threshold range; the purification system removes suspended particles, ion impurities and the like contained in the coolant by passing the coolant through a filter and an ion exchange resin to purify the coolant; the cold pipe section driven by the main coolant pump is connected with a volume control and purification system; the volume control system absorbs the change of the volume of the coolant which cannot be absorbed by the voltage stabilizer through charging and discharging according to the change of the volume of the coolant in the main loop; maintaining the water level of the potentiostat at a programmed position; part of the primary coolant flows into the bypass and through the purification system; the purification system purifies the main loop coolant, removes suspended particles in the coolant through filtration, and removes ionic impurities through ion exchange resin.
When the volume of the coolant of the main loop system is increased to a value that the coolant cannot be absorbed by the voltage stabilizer, a cold pipe section between a main coolant pump and a distribution pipe is responsible for leading out the coolant, the expanded coolant flows into the regenerative heat exchanger through a fourth diaphragm valve and a third check valve to be cooled, then flows through three throttling pressure reduction pore plates connected in parallel, the three groups of pore plates are controlled by a plurality of valve groups, the coolant after pressure reduction reaches the lower-drain heat exchanger through an eighth diaphragm valve to be cooled for the second time, an equipment water cooling system is connected with the lower-drain heat exchanger and exchanges heat with the coolant, and then flows into the purification system after passing through a third manual isolation valve, a third filter and a seventh diaphragm valve.
After coolant enters a purification system, the coolant enters two th and second mixed bed ion exchangers connected in parallel through an eighth gate valve and a ninth gate valve, radioactive ions are removed by ion exchange resin, then the coolant flows into a filter through a seventh gate valve and a second manual isolation valve, resin fragments and suspended particles in water are removed, then the coolant flows to a volume control box through a fifth diaphragm valve, when the temperature of the coolant subjected to temperature reduction and pressure reduction is higher than a preset value, a normally closed sixth diaphragm valve controls the coolant to directly flow into the volume control box through a bypass without flowing through the purification system, the volume control box is a buffer water box of a main loop, when the water level of the volume control box is higher than the preset value, the coolant is led out through a safety valve, otherwise, water is supplemented by a water supplementing device, the coolant is controlled by the sixth gate valve after reaching the volume control box, the coolant is led in from the volume control box through an upper charge pump, the coolant is driven to reach a regenerative heat exchanger through a fourth check valve, and then flows into a transitional control flow of the main loop, and the steam generator and the main loop are connected through a tenth coolant pump.
The invention provides auxiliary loops for a Tokamak fusion device cooling power generation system, supplements steps for the existing main loop and the existing secondary loop, ensures the operation of the main loop and the secondary loop, and has the technical advantages of stability and safety.
Drawings
FIG. 1 is a schematic diagram of the primary and secondary circuits of the present invention.
List of parts and reference numerals:
01 distribution pipe, 02 rd gate valve, 03 cladding, 04 second gate valve, 05 collection pipe, 06 th filter, 07 th 0 diaphragm valve, 08 steam generator, 09 third gate valve, 10 main coolant pump, 11 th check valve, 12 th fourth gate valve, 13 th manual isolation valve, 14 residual heat removal pump, 15 second check valve, 16 residual heat removal heat exchanger, 17 th second diaphragm valve, 18 th apparatus cooling water system, 19 pure water, 20 th fifth gate valve, 21 buffer tank, 22 th third diaphragm valve, 23 fourth diaphragm valve, 24 third check valve, 25 regenerative heat exchanger, 26 fourth check valve, 27 charge pump, 28 sixth gate valve, 29 volume control tank, 30 make-up water device, 31 rd safety valve, 32 th diaphragm valve, 33 th second filter, 34 seventh gate valve, 35 th manual isolation valve, 36 th 4 mixed bed ion exchanger, 37 eighth diaphragm valve, 38 ninth mixed bed ion gate valve, 39 th mixed bed ion gate valve, 40 sixth diaphragm valve, 41, 33 seventh diaphragm valve, 34 seventh diaphragm valve, 35 th manual isolation valve, 35 fifth diaphragm valve, 35 eighth diaphragm valve, 65, seventeenth diaphragm valve, fifth diaphragm valve, sixth diaphragm valve, 18 steam turbine, 35, sixth diaphragm valve.
Noun definition description
Header pipes, which primarily collect and merge the coolant in all cooling pipes in the cladding in each sector, are connected to the main circuit by main pipe system .
Distributing pipe for sending the coolant in the main loop to the cladding of each sector for circulation cooling according to the flow distribution of .
Pressure stabilizer-the equipment for controlling pressure and protecting overpressure of main loop, the pressure of main loop is about 15.5MPa when it is in steady operation, and when the system pressure is too large, it can make pressure relief protection by means of pressure stabilizer, and the pressure stabilizer must have enough volume to adapt to the volume fluctuation resulted from temp. change of coolant.
Steam generator-heat exchange equipment for transferring the heat generated by fusion device cladding to two-loop feed water to make it generate steam with constant temperature and pressure.
Main coolant pump-high speed running equipment for driving high temperature and high pressure coolant to circulate and transfer the heat of fusion device cladding to steam generator.
Pressure relief tank-a steam device used to condense and cool the pressure stabilizer discharge to the pressure relief tank when over-pressurized, preventing leakage of the main loop coolant.
Residual heat removal pump, a driving device that delivers coolant with residual heat to a heat exchanger for cooling.
Residual heat removal heat exchanger — is used to cool the coolant with the residual heat.
Pressure reducing orifice-a device used to reduce the pressure of the letdown stream below the operating pressure of the letdown heat exchanger.
Regenerative heat exchanger-is used for taking the coolant of upper charge as the cold source to carry on the heat recovery, carry on the first cooling to the lower leakage flow, prevent the apparatus vaporized.
The downward-discharging heat exchanger is a vaporization device used for carrying out secondary temperature reduction on downward-discharging flow to enable the downward-discharging flow to be lower than the temperature of a purification system and prevent secondary pressure reduction.
Mixed bed ion exchanger-equipment for adsorbing radioactive ions in coolant by mixing and filling anion and cation exchange resins according to ratio.
Cation-bed ion exchanger-a device for removing radioactive substances from coolant and purifying the coolant.
Volume control box-used for absorbing the volume change of the coolant that the stabiliser can not absorb, release the waste gas in the main loop.
Charge pump-a device for feeding purified coolant into the transition pipe section of the main circuit for circulation cooling.
Buffer tank-equipment for buffering the fluctuation of coolant volume in the main loop system and absorbing excessive coolant in the main loop.
Detailed Description
The coolant flows into the cladding 03 module at a pressure of 15.5MPa and a temperature of 285 ℃, absorbs nuclear heat generated in the cladding of the fusion device, opens a second gate valve 04, collects the coolant of each cladding module through a collecting pipe 05, collects the coolant into an filter 06 to filter out impurities such as particles in the coolant, enters the U-shaped heat transfer pipe of the steam generator 08 through a -th diaphragm valve 07, transfers the heat to a second loop feed water outside the U-shaped heat transfer pipe to change the coolant into saturated steam, passes through a third gate valve 09 and is driven by a main coolant pump 10, passes through a -th check valve 11, passes through a fourth gate valve 12, distributes the coolant through a flow of 01, returns to the cladding of the fusion device through a -th diaphragm valve 02 to be reheated, circulates in such a way, closed heat absorption and heat release circulation processes are formed, when the coolant in the main loop is excessive, the coolant can be introduced into a buffer tank 21 through the third diaphragm valve 22, and when the coolant is less than the coolant in the fifth diaphragm valve 22, the coolant can be replenished through a fifth diaphragm valve 19.
The divertor cooling circuit basically comprises an th heat exchanger 76, a th coolant pump 81 and a plurality of gate valves, which are described in the patent publication No. CN 105976873A: of future Tokamak fusion device internal component cooling power generation systems.
The number II is a secondary loop, the function of the secondary loop is to convert the steam of the steam generator 08 into electric energy, the feed water of the secondary loop absorbs the heat of the main loop to form steam, then the steam enters a steam turbine 68 to drive a power generation, the steam after the power generation is discharged into a condenser 71 to be condensed into water, a condensate pump 73 drives the water to pass through a second heat exchanger 87 in a vacuum chamber cooling loop and an -th heat exchanger 76 in a divertor cooling loop, the energy generated by the vacuum chamber and the divertor is used for preheating the cooling water of the secondary loop, and after the water is heated to the temperature and the pressure of , the water enters the steam generator 08 of the cladding layer to exchange energy with the steam generator, so that the closed circulation of the secondary loop is formed.
Auxiliary circuit-vacuum chamber cooling circuit
As shown in fig. 1, reference numeral iii is a vacuum chamber cooling circuit. The vacuum chamber cooling circuit mainly comprises a coolant pump 86, a second heat exchanger 87 and a plurality of gate valves. The heat energy generated by the heat exchanger is exchanged with the water on the outlet side of the condensate pump 73 of the second circuit by the second heat exchanger 87, and the feed water of the second circuit is preheated.
Auxiliary loop-residual heat removal system
As shown in FIG. 1, the residual heat removal system is numbered IV, when the fusion device cladding normally operates, the residual heat removal system is isolated for standby, namely, the manual isolation valve 13 which controls the residual heat removal system to be connected with the main loop main system is in a normally closed state, when the fusion device stops operating, residual power heat is removed by the steam generator 08 at first, and cooling of the fusion device cladding is guaranteed, only when the pressure and temperature of the coolant in the main loop are reduced to fixed threshold values when the second loop of the fusion device does not operate, the manual isolation valve 13 is opened to start the residual heat removal system, the residual heat removal system design component mainly comprises a residual heat removal pump 14, a residual heat removal heat exchanger 16, a corresponding valve pipeline and the like, the coolant is driven by the residual heat removal pump 14, flows through a second check valve 15, enters the residual heat removal heat exchanger 16 for cooling, a equipment cooling water system 18 which is connected with the residual heat removal heat exchanger 16 and exchanges energy with the coolant, and when the temperature and the pressure reach the input requirements of the cold coolant in the main loop, the residual heat removal system is opened, and the residual heat removal coolant enters the cold loop cooling system 17 for recycling.
Auxiliary circuit-pressure control and overpressure protection system
As shown in figure 1, the number V is a pressure control and overpressure protection system, the pressure change control of the coolant is required to be within an allowable range to ensure the operation safety of the system, the main components of the system comprise a voltage stabilizer 52 and a pressure relief box 58, the coolant passes through a heat pipe section of a main loop and is controlled by a tenth gate valve 51, after impurities are filtered by an filter 06, the coolant reaches the voltage stabilizer 52 through the tenth gate valve 51 (normally open), and the interior of the system contains sensors for detecting water level, steam temperature, water temperature and pressure, so that the sensors are used for detecting the sensors.
The regulator 52 has saturated water at the bottom and saturated steam at the top, the regulator 52 has an electric heater 53 at the bottom, when the pressure in the regulator 52 is too low or the water level is too high, water is evaporated by heating with the electric heater 53, when the pressure in the regulator 52 is too high or the water level is too low, the heater 53 is completely disconnected, the steam space at the upper end of the regulator 52 can be sprayed by introducing coolant from the cold pipe section of the main circuit, to maintain the temperature and chemical composition of the coolant in the regulator 52 uniform, to reduce the local thermal stress caused by thermal shock, the spray device 55 connected to the top of the regulator 52 is divided into a main spray and an auxiliary spray, the main spray line is connected to the outlet line of the main coolant pump 10, a fourth manual isolation valve 50 is provided, when the main coolant pump 10 is driven, the spray is injected into the top of the regulator 52 through the main spray line, the steam undersized space of the regulator 52 is injected into the main circuit, when the main circuit is operating normally, the fourth manual isolation valve 50 is opened to control the spray when the main coolant pump 10 fails, the ninth 48 is opened to maintain a small continuous spray flow rate to maintain the temperature in the pressure in the regulator 52 to maintain the pressure in the pressure tank, the thirteen continuous spray tank is connected to the pressure tank 58 to control the high pressure tank, the pressure tank 58 to prevent the condensate from passing through the medium, when the pressure tank 58, the condensate can be discharged, the condensate can be discharged to prevent the condensate from passing through the condensate tank, the condensate from passing through the condensate tank, when the condensate tank, the condensate tank 58, the condensate tank.
Auxiliary circuit-volume control and purification system
As shown in fig. 1, designated vi is a volume control and purification system. The volume control and purge system is connected to the cold pipe section driven by the main coolant pump 10. The volume control system maintains the water level of the pressurizer 52 in a programmed position by filling up and draining down to absorb the volume change of the coolant that the pressurizer 52 cannot absorb in response to the volume change of the coolant in the main circuit. Approximately 5% of the primary coolant flows into and through the purification system, which purifies the primary loop coolant, removes suspended particulate matter from the coolant via filtration, and removes ionic impurities via ion exchange resins.
The cold pipe section between the main coolant pump 10 and the distribution pipe 01 is responsible for drawing out the coolant when the main circuit system coolant volume increases to such an extent that the pressurizer 52 cannot absorb it. The expanded coolant flows into the regenerative heat exchanger 25 through the fourth diaphragm valve 23 and the third check valve 24 to be cooled, then passes through three throttling and pressure reducing orifice plates 47 connected in parallel, three groups of orifice plates are controlled by a plurality of valve groups, the coolant after pressure reduction passes through the eighth diaphragm valve 46 to reach the lower-drain heat exchanger 44 to be cooled for the second time, and a second equipment cooling water system 45 is connected with the lower-drain heat exchanger 44 and exchanges heat with the coolant. Then flows into the purification system through the third manual isolation valve 43, the third filter 42, and the seventh diaphragm valve 41.
After entering the purification system, the coolant is controlled to enter two parallel th and second mixed bed ion exchangers 36 and 39 through an eighth gate valve 37 and a ninth gate valve 38 to remove radioactive ions, then the coolant flows into a second filter 33 through a seventh gate valve 34 and a second manual isolation valve 35 to remove resin fragments and suspended particles in water, and then flows to the volume control box 29 through a fifth diaphragm valve 32. since the ion exchange resin cannot bear too high temperature, when the temperature of the coolant after temperature reduction and depressurization is too high, the sixth diaphragm valve 40 (normally closed) can control the coolant to bypass to directly flow into the volume control box without flowing through the purification system, the volume control box 29 mainly serves as a buffer water tank of the main loop, when the water level of the volume control box is too high, the coolant is led out through a th safety valve 31, otherwise, the system performs water replenishing through a water replenishing device 30, after the coolant reaches the volume control box 29, the coolant is controlled by a sixth gate valve 28, is introduced from the volume control box 29 through an upper charge pump 27, the coolant passes through a fourth diaphragm valve 25 to drive the coolant to flow regeneration heat exchanger 25, and then flows into a regeneration heat exchanger 49 connected with a heat exchanger 49.
The main loop and the secondary loop described in the present invention are not within the scope of the present invention. It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (8)
1, auxiliary loop for Tokamak fusion device cooling power generation system, connected to main loop, two loops, characterized in that:
comprises a vacuum chamber cooling loop, a waste heat discharge system, a pressure control and overpressure protection system and a volume control and purification system;
the vacuum chamber cooling loop exchanges energy with the secondary loop through a second heat exchanger, the waste heat discharge system is connected with the main loop through an manual isolation valve, the pressure control and overpressure protection system is connected with the main loop through a tenth gate valve, and the volume control and purification system is connected with the main loop through a fourth diaphragm valve;
the coolant water of the main loop flows through the fusion device cladding module to take away a large amount of nuclear heat generated by the fusion device, and the taken energy is used for generating electricity through the two loops; the auxiliary loop provides support for the main loop and the secondary loop, and safe and stable operation of the main loop and the secondary loop is ensured.
2. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 1, wherein:
the vacuum chamber cooling loop comprises a coolant pump second heat exchanger and a plurality of gate valves; the heat generated by the heat exchanger is exchanged with the feed water on the outlet side of the pump of the second loop through the second heat exchanger to preheat the feed water of the second loop.
3. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 1, wherein:
the fusion device comprises a fusion device, a residual heat discharging system and a manual isolating valve , wherein the fusion device comprises a fusion device body, a residual heat discharging system and a manual isolating valve , the fusion device body is connected with a th equipment cooling water system, the residual heat discharging system is started to take residual heat in a fusion device cladding when the fusion device is stopped, heat generated by nuclear reaction in the fusion device body is not completely taken away, the residual heat discharging system is started to take away the residual heat, the coolant is started to be discharged by the manual isolating valve , the coolant is driven by the residual heat discharging pump to flow through a check valve and enter a heat exchanger for cooling, the th equipment cooling water system is connected with the heat exchanger and exchanges energy with the coolant, and when the temperature and the pressure meet the input requirements of the coolant in a cold pipe section, the second diaphragm valve.
4. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 1, wherein:
the pressure control and overpressure protection system is used for adjusting dynamic pressure value fluctuation in normal operation of a main loop, performing pressure relief protection on the main loop system when a serious accident occurs, and ensuring safety of parts of the main loop system, and comprises a voltage stabilizer and a pressure relief box, wherein a coolant passes through a heat pipe section of the main loop and is controlled by a tenth gate valve, the coolant passes through a tenth gate valve after impurities are filtered by an filter and reaches the voltage stabilizer, sensors for detecting water level, steam temperature, water temperature and pressure are arranged in the pressure control and overpressure protection system and are used for detecting, when the fusion device has a serious accident, the pressure is rapidly increased, emergency pressure relief can be performed through a second safety valve at the top of the voltage stabilizer, and safety protection is performed on the main loop.
5. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 4, wherein:
the pressure stabilizer comprises a pressure stabilizer, a pressure release tank, a cooling water tank, an electric heater, a cooling agent inlet pipe, a main loop, a main spray pipe, a main spray diaphragm valve, a fourth manual isolation valve, a pressure release diaphragm valve, a fourteenth manual isolation valve, a cooling agent outlet pipe, a cooling agent discharge tank, a fourteenth manual isolation valve, a thirteenth manual isolation valve, a fourteenth manual isolation valve, a pressure release valve, a mixture tank, a fourteenth hydrogen discharge tank, a fourteenth manual release valve, a fourteenth manual isolation valve, a pressure release valve, a fourteenth manual release valve, a pressure release valve, a fourteenth hydrogen release valve, a pressure relief valve, a.
6. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 1, wherein:
the volume control and purification system is used for adjusting the volume fluctuation caused by the temperature change of the coolant in the main loop and purifying the coolant, and the volume control is used for absorbing the volume change of the coolant of the main loop which cannot be absorbed by the voltage stabilizer so that the water level of the voltage stabilizer fluctuates within a safety threshold range; the purification system removes suspended particles, ion impurities and the like contained in the coolant by passing the coolant through a filter and an ion exchange resin to purify the coolant; the cold pipe section driven by the main coolant pump is connected with a volume control and purification system; the volume control system absorbs the change of the volume of the coolant which cannot be absorbed by the voltage stabilizer through charging and discharging according to the change of the volume of the coolant in the main loop; maintaining the water level of the potentiostat at a programmed position; part of the primary coolant flows into the bypass and through the purification system; the purification system purifies the main loop coolant, removes suspended particles in the coolant through filtration, and removes ionic impurities through ion exchange resin.
7. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 6, wherein:
when the volume of the coolant of the main loop system is increased to a value that the coolant cannot be absorbed by the voltage stabilizer, a cold pipe section between a main coolant pump and a distribution pipe is responsible for leading out the coolant, the expanded coolant flows into the regenerative heat exchanger through a fourth diaphragm valve and a third check valve to be cooled, then flows through three throttling pressure reduction pore plates connected in parallel, the three groups of pore plates are controlled by a plurality of valve groups, the coolant after pressure reduction reaches the lower-drain heat exchanger through an eighth diaphragm valve to be cooled for the second time, an equipment water cooling system is connected with the lower-drain heat exchanger and exchanges heat with the coolant, and then flows into the purification system after passing through a third manual isolation valve, a third filter and a seventh diaphragm valve.
8. An auxiliary loop for a tokamak fusion device cooled power generation system as claimed in claim 7, wherein:
after coolant enters a purification system, the coolant enters two th and second mixed bed ion exchangers connected in parallel through an eighth gate valve and a ninth gate valve, radioactive ions are removed by ion exchange resin, then the coolant flows into a filter through a seventh gate valve and a second manual isolation valve, resin fragments and suspended particles in water are removed, then the coolant flows to a volume control box through a fifth diaphragm valve, when the temperature of the coolant subjected to temperature reduction and pressure reduction is higher than a preset value, a normally closed sixth diaphragm valve controls the coolant to directly flow into the volume control box through a bypass without flowing through the purification system, the volume control box is a buffer water box of a main loop, when the water level of the volume control box is higher than the preset value, the coolant is led out through a safety valve, otherwise, water is supplemented by a water supplementing device, the coolant is controlled by the sixth gate valve after reaching the volume control box, the coolant is led in from the volume control box through an upper charge pump, the coolant is driven to reach a regenerative heat exchanger through a fourth check valve, and then flows into a transitional control flow of the main loop, and the steam generator and the main loop are connected through a tenth coolant pump.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111963267A (en) * | 2020-08-21 | 2020-11-20 | 安徽大学 | Supercritical carbon dioxide power circulation system and method for 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 |
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| CN111963267B (en) * | 2020-08-21 | 2022-09-27 | 安徽大学 | Supercritical carbon dioxide power circulation system and method for 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 |
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