CN112999869A - Device and method for continuously extracting tritium from fusion reactor liquid metal lithium-lead alloy - Google Patents
Device and method for continuously extracting tritium from fusion reactor liquid metal lithium-lead alloy Download PDFInfo
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- JWZCKIBZGMIRSW-UHFFFAOYSA-N lead lithium Chemical compound [Li].[Pb] JWZCKIBZGMIRSW-UHFFFAOYSA-N 0.000 title claims abstract description 155
- 229910001338 liquidmetal Inorganic materials 0.000 title claims abstract description 154
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 title claims abstract description 79
- 229910052722 tritium Inorganic materials 0.000 title claims abstract description 79
- 230000004927 fusion Effects 0.000 title claims abstract description 45
- 238000000034 method Methods 0.000 title claims abstract description 29
- 229910000978 Pb alloy Inorganic materials 0.000 title claims abstract description 21
- 239000010935 stainless steel Substances 0.000 claims abstract description 93
- 229910001220 stainless steel Inorganic materials 0.000 claims abstract description 93
- 239000012159 carrier gas Substances 0.000 claims abstract description 55
- 239000007789 gas Substances 0.000 claims abstract description 41
- 239000007788 liquid Substances 0.000 claims abstract description 29
- 238000005253 cladding Methods 0.000 claims abstract description 23
- 238000000605 extraction Methods 0.000 claims abstract description 19
- 230000006698 induction Effects 0.000 claims abstract description 16
- 238000003860 storage Methods 0.000 claims abstract description 10
- 239000011148 porous material Substances 0.000 claims description 33
- 239000012528 membrane Substances 0.000 claims description 24
- 238000000926 separation method Methods 0.000 claims description 15
- 229910052739 hydrogen Inorganic materials 0.000 claims description 11
- 239000001257 hydrogen Substances 0.000 claims description 11
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 9
- 238000009736 wetting Methods 0.000 claims description 9
- 230000009471 action Effects 0.000 claims description 8
- 239000001307 helium Substances 0.000 claims description 8
- 229910052734 helium Inorganic materials 0.000 claims description 8
- 238000004817 gas chromatography Methods 0.000 claims description 7
- 238000000746 purification Methods 0.000 claims description 7
- 238000006243 chemical reaction Methods 0.000 claims description 6
- 238000005372 isotope separation Methods 0.000 claims description 5
- 238000010926 purge Methods 0.000 claims description 5
- 238000005516 engineering process Methods 0.000 claims description 3
- 238000010438 heat treatment Methods 0.000 claims description 3
- 239000012535 impurity Substances 0.000 claims description 3
- 239000000463 material Substances 0.000 claims description 3
- 238000012545 processing Methods 0.000 claims description 3
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 2
- 238000001179 sorption measurement Methods 0.000 claims 2
- 238000013375 chromatographic separation Methods 0.000 claims 1
- 230000008014 freezing Effects 0.000 claims 1
- 238000007710 freezing Methods 0.000 claims 1
- 238000003466 welding Methods 0.000 claims 1
- 230000007547 defect Effects 0.000 abstract description 4
- 229910052751 metal Inorganic materials 0.000 description 5
- 239000002184 metal Substances 0.000 description 5
- 238000013461 design Methods 0.000 description 4
- 238000009395 breeding Methods 0.000 description 3
- 230000001488 breeding effect Effects 0.000 description 3
- 230000008595 infiltration Effects 0.000 description 3
- 238000001764 infiltration Methods 0.000 description 3
- 150000002431 hydrogen Chemical class 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 238000011084 recovery Methods 0.000 description 2
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000005255 beta decay Effects 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007499 fusion processing Methods 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 229910052744 lithium Inorganic materials 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D61/00—Processes of separation using semi-permeable membranes, e.g. dialysis, osmosis or ultrafiltration; Apparatus, accessories or auxiliary operations specially adapted therefor
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- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
- C01B4/00—Hydrogen isotopes; Inorganic compounds thereof prepared by isotope exchange, e.g. NH3 + D2 → NH2D + HD
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- General Health & Medical Sciences (AREA)
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Abstract
The invention relates to a device and a method for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy, which comprises a fusion reactor liquid metal lithium-lead cladding, a liquid metal lithium-lead loop, a carrier gas storage tank, a first gas control valve, a mass flow controller, a first digital pressure meter, a second gas control valve, a gas chromatograph, a vacuum pump, a first electromagnetic flowmeter, a k-type armored thermocouple, a loop control valve, a porous stainless steel film, a liquid metal lithium-lead cache tank, a second digital pressure meter, a second electromagnetic flowmeter, a high-temperature electromagnetic pump, a data acquisition card, a computer, a full-density stainless steel pipe, an induction type liquid level meter, a carrier gas inlet pipeline and a carrier gas outlet pipeline. The invention can realize the high-mass flow rate continuous extraction of tritium and solve the defects of complex structure, high cost and low tritium extraction efficiency in the prior art.
Description
Technical Field
The invention belongs to the field of advanced nuclear reactor nuclear fuel, and particularly relates to a device and a method for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy.
Background
Tritium is an isotope of hydrogen, an important fuel for fusion reactions. Tritium is easy to produce beta decay under natural conditions, so that the tritium is very low in natural environment (the abundance is only 1 × 10)-16Globally amounting to about 2 kg). To realize the continuous operation of fusion reaction, it must ensure that tritium can be self-sufficient in the fusion process, and the process is mainly completed by the breeding process of tritium in the fusion reactor cladding. The cladding can be divided into solid cladding and liquid cladding according to the different forms of the tritium breeding agent. The liquid cladding mainly uses a liquid metal alloy containing lithium as a tritium breeding material, wherein the liquid metal lithium lead has the advantages of high thermal conductivity, low tritium solubility and low reaction activity with oxygen and water, and is widely applied to the existing liquid metal cladding.
At present, the method for continuously extracting tritium from liquid metal lithium-lead alloy mainly comprises the following steps: a metal film (Nb, Zr) infiltration method (Fusion Engineering and Design, 1991,18:61) in which a vacuum infiltration window made of Nb or Nb/Zr is arranged at the bypass position of a lithium lead cooling tube, and tritium is extracted by the difference of the tritium concentration at the two sides of the metal film; the method comprises the steps of using NaK or Na as an intermediate heat medium, enabling tritium to penetrate through the intermediate heat medium through an intermediate heat exchanger or a double-wall heat exchanger, filling a cold trap with meshes, arranging the cold trap at a bypass position of a NaK or Na loop, and realizing continuous recovery of the tritium; a gas-liquid countercurrent extraction packed column method (Fusion Engineering and Design, 2012,87: 1014-; the bubbler method (nuclear fusion and plasma physics, 2013,33:83-87) is characterized in that liquid metal lithium lead is shunted through a packed tower and forms a liquid film, inert gas is introduced from the bottom of the packed tower at designed flow and pressure and is bubbled in lithium lead alloy flowing in the reverse direction to form small bubbles with large specific surface area, and tritium is extracted through isotope exchange migration generated on a gas-liquid interface.
Among the above methods of extracting tritium, the metal film permeation method has a risk of leakage of lithium lead into vacuum, and may generate hydrogen embrittlement due to high hydrogen solubility of the structural material, resulting in low durability. The cold trap method of the intermediate heat medium passage adopts NaK or Na as the intermediate heat medium, and the tritium has higher concentration when penetrating into the intermediate heat medium, so that the danger of environmental leakage exists. The gas-liquid countercurrent extraction packed tower method seriously affects the extraction efficiency of tritium because the tritium stays in the vacuum chamber for a short time. The bubbler method is a widely used tritium extraction method at present, but the method needs to build a large-scale experimental device comprising a packed bed and a bubbler, and has the disadvantages of complex system, high cost and low recovery efficiency (Fusion Engineering and Design, 2018,135: 74-80). In the development of the fusion reactor technology, the research and development of a device and a technology capable of efficiently and continuously extracting tritium are very critical to the design of a fusion reactor cladding.
In conclusion, the prior art has the defects of complex structure, high cost and low tritium extraction efficiency.
Disclosure of Invention
The technical problem to be solved by the invention is as follows: the device and the method overcome the defects of the prior art, provide the porous stainless steel film device and the method suitable for continuously extracting tritium from the fusion reactor liquid metal lithium-lead alloy, realize the high-mass-flow-rate continuous extraction of tritium, and solve the defects of complex structure, high cost and low tritium extraction efficiency in the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows:
the invention relates to a device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy, which comprises a fusion reactor liquid metal lithium-lead cladding, a liquid metal lithium-lead loop, a carrying gas storage tank, a first gas control valve, a mass flow controller, a first digital pressure meter, a second gas control valve, a gas chromatography analyzer, a vacuum pump, a first electromagnetic flowmeter, a k-type armored thermocouple, a loop control valve, a porous stainless steel film, a liquid metal lithium-lead cache tank, a second digital pressure meter, a second electromagnetic flowmeter, a high-temperature electromagnetic pump, a data acquisition card, a computer, a full-density stainless steel pipe, an induction type liquid level meter, a carrying gas inlet pipeline and a carrying gas outlet pipeline; a mother pipe of a fusion reactor liquid metal lithium lead cladding is connected with an inlet section of a liquid metal lithium lead loop, a liquid metal lithium lead cache tank is arranged in the middle of an outlet section of the liquid metal lithium lead loop, k-shaped armored thermocouples are uniformly arranged in liquid metal lithium lead at the bottom of the cache tank, a porous stainless steel film is welded on a full-dense stainless steel pipe which is welded at the top of the liquid metal lithium lead cache tank, the porous stainless steel film is completely immersed in the liquid metal lithium lead of the liquid metal lithium lead cache tank, an induction type liquid level meter is positioned on the liquid level of the liquid metal lithium lead in the cache tank, an outlet of a carrier gas storage tank is connected with a first gas control valve and enters a carrier gas inlet pipeline after passing through a mass flow controller, a first digital is arranged at the upper part of the carrier gas inlet pipeline, the carrier gas inlet pipeline is welded at the upper part of the full-dense stainless steel pipe, and a right opening of the full, then a second gas control valve, a gas chromatographic analyzer, a vacuum pump and a carrier gas tritium separation system are sequentially connected, a first electromagnetic flowmeter is connected with a loop control valve, the loop control valve is connected to the inlet of a liquid metal lithium lead buffer tank, a second digital pressure gauge is arranged at the upper part of the liquid metal lithium lead buffer tank, the outlet of the liquid metal lithium lead buffer tank is connected with the second electromagnetic flowmeter, the high-temperature electromagnetic pump is connected with the rear part of the fusion reactor, the outlet end of the high-temperature electromagnetic pump is connected with the inlet of a main pipe of the fusion reactor liquid metal lithium lead cladding, the input end of the data acquisition card is respectively connected with the mass flow controller, the first digital pressure meter, the gas chromatographic analyzer, the vacuum pump, the first electromagnetic flowmeter, the k-type armored thermocouple, the second digital pressure meter, the second electromagnetic flowmeter, the high-temperature electromagnetic pump and the induction type liquid level meter, and the output end of the data acquisition card is connected with the computer.
The pore size of the porous stainless steel film is determined by calculation of a Washburn equation, liquid metal lithium lead shows non-infiltration liquid on the surface of the stainless steel under the pore size condition, at the moment, the liquid metal lithium lead forms a gas-liquid interface at the pore of the porous stainless steel film, and tritium can be transmitted to the inside of the porous stainless steel film from the liquid metal lithium lead through diffusion of the gas-liquid interface.
The carrier gas tritium separation system comprises a purification system, a hydrogen helium separation system and a hydrogen isotope separation system. The carrier gas enters a purification system under the action of a vacuum pump, an outlet of the purification system is connected with a hydrogen-helium separation system, and an outlet of the hydrogen-helium separation system is connected with a hydrogen isotope separation system.
The invention also provides a method for continuously extracting tritium from the fusion reactor liquid metal lithium-lead alloy, which utilizes the porous stainless steel film to extract tritium from the liquid metal lithium-lead alloy in a carrier gas purging mode, and specifically comprises the following steps:
step S1: in the fusion reaction process, tritium-loaded high-temperature liquid metal lithium lead in a fusion reactor liquid metal lithium lead cladding is injected into an inlet section of a liquid metal lithium lead loop from a cladding main pipe, a first electromagnetic flowmeter measures the mass flow rate of the liquid metal lithium lead loop in a pipeline, and a loop control valve can continuously adjust the mass flow rate of the liquid metal lithium lead flowing into a liquid metal lithium lead cache tank;
step S2: under the action of the driving force of the high-temperature electromagnetic pump, liquid metal lithium lead is injected into a liquid metal lithium lead cache tank, the temperature of the liquid metal lithium lead is measured by 3 k-type armored thermocouples at the bottom of the cache tank in real time, the height of the liquid metal lithium lead is measured by an induction type liquid level meter at the top of the cache tank, the pressure of the liquid metal lithium lead in the cache tank is measured by a second digital pressure meter, and the mass flow rate of an outlet of the liquid metal lithium lead cache tank is measured by a second electromagnetic flow meter;
step S3: the data acquisition card acquires digital signals of a first digital pressure gauge, a gas chromatographic analyzer, a vacuum pump, a first electromagnetic flowmeter, a k-type armored thermocouple, a second digital pressure gauge, a second electromagnetic flowmeter, a high-temperature electromagnetic pump and an induction type liquid level meter in real time, and transmits the digital signals to a computer through a bus for storage, display and processing, so as to provide input parameters for the computer to control the flow velocity of liquid metal lithium lead and the mass flow rate of carrier band gas in the porous stainless steel film in real time;
step S4: before the porous membrane stainless steel membrane starts to work, firstly, purging the inside of the fully-sealed stainless steel tube and the porous stainless steel membrane by using carrier gas to remove impurity gas in the fully-sealed stainless steel tube and the porous stainless steel membrane; and then heating the porous stainless steel film and then immersing the porous stainless steel film into liquid metal lithium lead, wherein tritium penetrates into the porous stainless steel film from the liquid metal lithium lead through pores on the porous stainless steel film due to the fact that the concentration of the tritium in the liquid metal lithium lead is different from that in the porous stainless steel film, then is carried out of the fully-dense stainless steel tube through carrier gas, and then enters a carrier gas tritium separation system under the action of a vacuum pump to complete tritium extraction, a second gas control valve can continuously adjust the mass flow rate of the carrier gas, and a gas chromatograph can detect the concentration of the tritium in the carrier gas in real time.
Further, in the step S2, the fully-dense stainless steel tube is welded to the middle of the top of the liquid metal lithium lead buffer tank.
Further, the pore size of the pores on the porous stainless steel membrane in step S3 is determined by the pressure difference between the liquid metal lithium lead and the carrier gas, the surface tension of the liquid metal lithium lead, and the wetting angle of the liquid metal lithium lead on the stainless steel surface, and they are related as follows:
wherein D is the pore diameter of the porous stainless steel membrane, PGAnd PLAre respectively liquidThe pressure of the liquid metal lithium lead and the carrier gas on the two sides of the pore space, theta is the wetting angle of the liquid metal lithium lead and the stainless steel surface, and gamma is the surface tension of the liquid metal lithium lead.
Compared with the existing tritium extraction method, the invention has the advantages that: the device of the invention is characterized in that the porous stainless steel film is placed in liquid metal lithium lead, and the tritium isotope is transported through a gas-liquid interface, so that the mass transfer resistance is far lower than that of a metal film. Compared with the existing tritium extraction technology by a metal film permeation method, the tritium extraction efficiency measured by the method is improved by 1.5-2.8 times. Therefore, the method has the remarkable advantages of simple structure, low cost and high tritium extraction efficiency, and can effectively solve the problem of continuous and efficient extraction of tritium from the fusion reactor liquid metal lithium lead.
Drawings
FIG. 1 is a schematic diagram of a device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy.
Detailed Description
The present invention will be described in detail below with reference to the accompanying drawings and examples.
As shown in figure 1, the device for continuously extracting tritium from fusion reactor liquid metal lithium lead alloy consists of a fusion reactor liquid metal lithium lead cladding 1, a liquid metal lithium lead loop 2, a carrying gas storage tank 3, a first gas control valve 4, a mass flow controller 5, a first digital pressure gauge 6, a second gas control valve 7, a gas chromatography analyzer 8, a vacuum pump 9, a first electromagnetic flowmeter 10, a k-type armored thermocouple 11, a loop control valve 12, a porous stainless steel film 13, a liquid metal lithium lead cache tank 14, a second digital pressure gauge 15, a second electromagnetic flowmeter 16, a high-temperature electromagnetic pump 17, a data acquisition card 18, a computer 19, a full-density stainless steel pipe 20, an induction type liquid level meter 21, a carrying gas inlet pipeline 22 and a carrying gas outlet pipeline 23.
A mother pipe of a fusion reactor liquid metal lithium lead cladding layer 1 is connected with an inlet section of a liquid metal lithium lead loop 2, a liquid metal lithium lead cache tank 14 is arranged in the middle of an outlet section of the liquid metal lithium lead loop, k-type armored thermocouples 11 are uniformly arranged in liquid metal lithium lead at the bottom of the cache tank, a porous stainless steel film 13 is welded on a full-density stainless steel pipe 20, the full-density stainless steel pipe 20 is welded at the top of the liquid metal lithium lead cache tank 14, the porous stainless steel film 13 is completely immersed in the liquid metal lithium lead of the liquid metal lithium lead cache tank 14, an induction type liquid level meter 21 is positioned on the liquid metal lithium lead liquid level in the cache tank, an outlet of a carrier gas storage tank 3 is connected with a first gas control valve 4 and enters a carrier gas inlet pipeline 22 after passing through a mass flow controller 5, a first digital 6 is arranged at the upper part of the carrier gas inlet pipeline 22, the carrier gas inlet pipeline 22 is welded at the, the right opening of a full-dense stainless steel pipe 20 is connected with a carrier gas outlet pipeline 23, and then is sequentially connected with a second gas control valve 7, a gas chromatography 8, a vacuum pump 9 and a carrier gas tritium separation system, a first electromagnetic flowmeter 10 is connected with a loop control valve 12, the loop control valve 12 is connected with an inlet of a liquid metal lithium lead cache tank 14, a second digital pressure gauge 15 is installed at the upper part of the liquid metal lithium lead cache tank 14, an outlet of the liquid metal lithium lead cache tank 14 is connected with a second electromagnetic flowmeter 16, and then is connected with a high-temperature electromagnetic pump 17, an outlet end of the high-temperature electromagnetic pump 17 is connected with a main pipe inlet of a fusion reactor liquid metal lithium lead cladding 1, an input end of a data 18 is respectively connected with a mass flow controller 5, a first digital pressure gauge 6, the gas chromatography 8, the vacuum pump 9, the first electromagnetic flowmeter 10 and a k-type armored thermocouple 11, The second digital pressure gauge 15, the second electromagnetic flowmeter 16, the high-temperature electromagnetic pump 17 and the induction type liquid level meter 21, and the output end of the data acquisition card 18 is connected with the computer 19.
The method comprises the following concrete steps:
step S1: in the fusion reaction process, tritium-loaded high-temperature liquid metal lithium lead in a fusion reactor liquid metal lithium lead cladding layer 1 is injected into an inlet section of a liquid metal lithium lead loop 2 from a cladding main pipe, a first electromagnetic flowmeter 10 measures the mass flow rate of the liquid metal lithium lead loop in a pipeline, and a loop control valve 12 can continuously adjust the mass flow rate of the liquid metal lithium lead flowing into a liquid metal lithium lead cache tank 14;
step S2: under the action of the driving force of the high-temperature electromagnetic pump 17, liquid metal lithium lead is injected into a liquid metal lithium lead cache tank 14, the temperature of the liquid metal lithium lead is measured in real time by 3 k-type armored thermocouples 11 at the bottom of the cache tank, the height of the liquid metal lithium lead is measured by an induction type liquid level meter 21 at the top of the cache tank, the pressure of the liquid metal lithium lead in the cache tank is measured by a second digital pressure meter 15, and the mass flow rate of an outlet of the liquid metal lithium lead cache tank is measured by a second electromagnetic flow meter 16;
step S3: the data acquisition card acquires digital signals of a first digital pressure gauge, a gas chromatographic analyzer, a vacuum pump, a first electromagnetic flowmeter, a k-type armored thermocouple, a second digital pressure gauge, a second electromagnetic flowmeter, a high-temperature electromagnetic pump and an induction type liquid level meter in real time, and transmits the digital signals to a computer through a bus for storage, display and processing, so as to provide input parameters for the computer to control the flow velocity of liquid metal lithium lead and the mass flow rate of carrier band gas in the porous stainless steel film in real time;
step S4: before the porous membrane stainless steel membrane starts to work, firstly, purging the inside of the fully-sealed stainless steel tube and the porous stainless steel membrane by using carrier gas to remove impurity gas in the fully-sealed stainless steel tube and the porous stainless steel membrane; and then heating the porous stainless steel film and then immersing the porous stainless steel film into liquid metal lithium lead, wherein tritium penetrates into the porous stainless steel film from the liquid metal lithium lead through pores on the porous stainless steel film due to the fact that the concentration of the tritium in the liquid metal lithium lead is different from that in the porous stainless steel film, then the tritium is carried out of the fully-sealed stainless steel tube through a carrier gas, a second gas control valve continuously adjusts the mass flow rate of the carrier gas, a gas chromatographic analyzer detects the concentration of the tritium in the carrier gas in real time, and the carrier gas finally enters a carrier gas tritium separation system under the action of a vacuum pump to complete tritium extraction.
In the step S2, the fully-sealed stainless steel tube 20 is welded to the middle of the top of the liquid metal lithium lead buffer tank 14.
In the step S3, the pore size of the porous stainless steel membrane 13 is determined by the pressure difference between the liquid metal lithium lead and the carrier gas, the surface tension of the liquid metal lithium lead, and the wetting angle of the liquid metal lithium lead on the stainless steel surface, and the relationship between the surface tension of the liquid metal lithium lead, the wetting angle of the liquid metal lithium lead on the stainless steel surface, the pressure difference between the liquid metal lithium lead and the carrier gas on the two sides of the pore, and the pore size of the pore on the porous stainless steel membrane is as follows:
wherein D is the pore diameter of the pores on the porous stainless steel membrane, PGAnd PLThe pressures of the liquid metal lithium lead and the carrier gas on the two sides of the pore are respectively, theta is the wetting angle of the liquid metal lithium lead and the stainless steel surface, and gamma is the surface tension of the liquid metal lithium lead.
The above description is only an example of the present invention and is not intended to limit the present invention, and various modifications and changes may be made to the present invention by those skilled in the art. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (9)
1. The utility model provides a device of tritium is drawed in succession from fusion reactor liquid metal lithium lead alloy which characterized in that: the device comprises a fusion reactor liquid metal lithium lead cladding (1), a liquid metal lithium lead loop (2), a carrier gas storage tank (3), a first gas control valve (4), a mass flow controller (5), a first digital pressure gauge (6), a second gas control valve (7), a gas chromatography analyzer (8), a vacuum pump (9), a first electromagnetic flowmeter (10), a k-type armored thermocouple (11), a loop control valve (12), a porous stainless steel membrane (13), a liquid metal lithium lead cache tank (14), a second digital pressure gauge (15), a second electromagnetic flowmeter (16), a high-temperature electromagnetic pump (17), a data acquisition card (18), a computer (19), a full-density stainless steel pipe (20), an induction type liquid level meter (21), a carrier gas inlet pipeline (22) and a carrier gas outlet pipeline (23);
one end of a fusion reactor liquid metal lithium lead cladding (1) is sequentially connected with an inlet of a liquid metal lithium lead loop (2), a first electromagnetic flowmeter (10), a loop control valve (12) and a liquid metal lithium lead cache tank (14), a fully-sealed stainless steel pipe (20) is welded at the top end outside the liquid metal lithium lead cache tank (14), a porous stainless steel film (13) is connected with the lower end of the fully-sealed stainless steel pipe (20), and the porous stainless steel film is immersed into the liquid metal lithium lead cache tank (14) during working; the second digital pressure gauge (15) is located at the upper end of the outside of the liquid metal lithium lead cache tank (14), the k-type armored thermocouple (11) is located at the bottom end of the inside of the liquid metal lithium lead cache tank (14), the induction type liquid level gauge (21) is located at the upper end of the inside of the liquid metal lithium lead cache tank (14), one side opening of the fully-sealed stainless steel pipe (20) is sequentially connected with a carrier gas outlet pipeline (23), a second gas control valve (7), a gas chromatography analyzer (8) and a vacuum pump (9), an outlet of the vacuum pump (9) is connected to a carrier gas tritium separation system, the carrier gas storage tank (3) is sequentially connected with a first gas control valve (4), a mass flow controller (5), a gas inlet pipeline (22) and the fully-sealed stainless steel pipe (20), the first digital pressure gauge (6) is located at the upper end of the gas pipeline inlet pipeline (22), an outlet of the liquid metal lithium lead cache tank (14) is sequentially connected with a second electromagnetic, The inlet of high temperature electromagnetic pump (17) and fusion reactor liquid metal lithium lead cladding (1), the input of data acquisition card (18) is connected mass flow controller (5) respectively, first digital pressure gauge (6), gas chromatography appearance (8), vacuum pump (9), first electromagnetic flowmeter (10), k type armoured thermocouple (11), second digital pressure gauge (15), second electromagnetic flowmeter (16), high temperature electromagnetic pump (17) and induction type level gauge (21), the output of data acquisition card (18) is connected with computer (19).
2. The device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy according to claim 1, is characterized in that: the carrier gas tritium separation system comprises a purification system, a hydrogen-helium separation system and a hydrogen isotope separation system; the carrier gas enters the purification system under the action of the vacuum pump, an outlet of the purification system is connected with an inlet of the hydrogen-helium separation system, and an outlet of the hydrogen-helium separation system is connected with the hydrogen isotope separation system. The purification system adopts a low-temperature freezing technology to separate tritium water in the carrier gas, the hydrogen-helium separation module adopts a low-temperature adsorption mode to adsorb hydrogen isotope gas from the carrier gas, and the hydrogen isotope gas obtained by adsorption adopts a chromatographic separation method to extract tritium in the hydrogen isotope separation module.
3. The device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy according to claim 1, is characterized in that: the carrier gas is helium.
4. The device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy according to claim 1, is characterized in that: the porous stainless steel membrane is of a hollow cylindrical structure, the structural material is S31603 stainless steel, pores with the same size are uniformly distributed on the side surface of the cylindrical stainless steel, the pore diameter of each pore is 2.6 mu m, the pores are communicated with the outside, and the porosity on the side surface of the cylindrical stainless steel is 35%.
5. The device for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy according to claim 1, is characterized in that: the liquid metal lithium lead forms a gas-liquid interface at the pore of the porous stainless steel membrane.
6. The apparatus of claim 4 for continuous extraction of tritium from a fusion reactor liquid metal lithium-lead alloy, wherein: the pore size of pores on the porous stainless steel membrane is determined by calculation of a Washburn equation, and under the condition of the pore size, liquid metal lithium lead is non-wetting liquid on the surface of the stainless steel.
7. The apparatus of claim 5 for continuous extraction of tritium from a fusion reactor liquid metal lithium-lead alloy, wherein: the pore size of the pores on the porous stainless steel membrane (13) is determined by the pressure difference between liquid metal lithium lead and carrier gas, the surface tension of the liquid metal lithium lead and the wetting angle of the liquid metal lithium lead on the stainless steel surface, and the relationship between the surface tension of the liquid metal lithium lead, the wetting angle of the liquid metal lithium lead on the stainless steel surface, the pressure difference between the liquid metal lithium lead and the carrier gas on the two sides of the pores and the pore size of the pores on the porous stainless steel membrane is as follows:
wherein D is the pore diameter of the pores on the porous stainless steel membrane, PGAnd PLThe pressures of the liquid metal lithium lead and the carrier gas on the two sides of the pore are respectively, theta is the wetting angle of the liquid metal lithium lead and the stainless steel surface, and gamma is the surface tension of the liquid metal lithium lead.
8. A method for continuously extracting tritium from fusion reactor liquid metal lithium-lead alloy is characterized in that: tritium is extracted from liquid metal lithium lead by utilizing a porous stainless steel film and a carrier gas purging mode, and the method comprises the following steps:
step S1: in the fusion reaction process, injecting liquid metal lithium lead in a fusion reactor liquid metal lithium lead cladding into an inlet section of a liquid metal lithium lead loop from a cladding main pipe, measuring the mass flow rate of the liquid metal lithium lead loop in a pipeline by a first electromagnetic flowmeter, and continuously adjusting the mass flow rate of the liquid metal lithium lead flowing into a cache tank by a loop control valve;
step S2: liquid metal lithium lead is injected into a liquid metal lithium lead cache tank under the action of the driving force of a high-temperature electromagnetic pump, the temperature of the liquid metal lithium lead is measured by 3 k-type armored thermocouples at the bottom of the cache tank in real time, the height of the liquid metal lithium lead is measured by an induction type liquid level meter at the top of the cache tank, the pressure of the liquid metal lithium lead in the cache tank is measured by a second digital pressure meter, and the mass flow rate of an outlet of the liquid metal lithium lead cache tank is measured by a second electromagnetic flow meter;
step S3: the data acquisition card acquires digital signals of a first digital pressure gauge, a gas chromatographic analyzer, a vacuum pump, a first electromagnetic flowmeter, a k-type armored thermocouple, a second digital pressure gauge, a second electromagnetic flowmeter, a high-temperature electromagnetic pump and an induction type liquid level meter in real time, transmits the digital signals to a computer through a bus for storage, display and processing, and provides input parameters for the computer to control the flow velocity of liquid metal lithium lead and the mass flow rate of carrier gas in the porous stainless steel film in real time so as to extract tritium;
step S4: before the porous membrane stainless steel membrane starts to work, firstly, purging the inside of the fully-sealed stainless steel tube and the porous stainless steel membrane by using carrier gas to remove impurity gas in the fully-sealed stainless steel tube and the porous stainless steel membrane; and then heating the porous stainless steel film and then immersing the porous stainless steel film into liquid metal lithium lead, wherein tritium penetrates into the porous stainless steel film from the liquid metal lithium lead through pores on the porous stainless steel film due to the fact that the concentration of the tritium in the liquid metal lithium lead is different from that in the porous stainless steel film, then the tritium is carried out of the fully-sealed stainless steel tube through a carrier gas, a second gas control valve continuously adjusts the mass flow rate of the carrier gas, a gas chromatographic analyzer detects the concentration of the tritium in the carrier gas in real time, and the carrier gas finally enters a carrier gas tritium separation system under the action of a vacuum pump to complete tritium extraction.
9. The method for continuously extracting tritium from a fusion reactor liquid metal lithium-lead alloy according to claim 8, wherein the method comprises the following steps: and in the step S2, welding the full-density stainless steel pipe in the middle of the top of the liquid metal lithium lead buffer tank.
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