CN203552711U - Tritium breeding blanket system based on lithium deuteroxide heavy water solution - Google Patents

Tritium breeding blanket system based on lithium deuteroxide heavy water solution Download PDF

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CN203552711U
CN203552711U CN201320608436.XU CN201320608436U CN203552711U CN 203552711 U CN203552711 U CN 203552711U CN 201320608436 U CN201320608436 U CN 201320608436U CN 203552711 U CN203552711 U CN 203552711U
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tritium
deuterium
lithia
aqueous solution
propagation
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罗天勇
张建利
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Abstract

The utility model relates to a tritium breeding blanket system based on a lithium deuteroxide heavy water solution. The tritium breeding blanket system consists of a tritium breeding blanket body, a primary loop system and a tritium enrichment system. A heavy water saturated solution of lithium deuteroxide is used as a tritium breeder and a coolant. Since the system unifies the tritium breeder and the coolant, a blanket structure is simplified and the manufacturing of the blanket body is facilitated; since the tritium breeder has flowability, online refueling is easy to realize. Compared with a conventional liquid state blanket system, the problems of magnetic flow caused by flowing of liquid metals and corrosion of structural materials caused by the liquid metals are overcome, and the safety of the cladding system is raised. A primary loop and heavy water tritium extraction technology related to the system have already been applied on heavy water reactors in a large scale. Compared with the existing solid and liquid tritium breeding blanket scheme, the technology is mature and reliable.

Description

Tritium propagation cladding systems based on deuterium Lithia heavy aqueous solution
Technical field
The utility model belongs to fusion tritium propagation cladding technique field, be specifically related to a kind of new fusion tritium propagation cladding systems scheme, for solving the self-holding problem of tritium of deuterium tritium fusion technology research device, fusion engineering experimental reactor and HCSB-DEMO after international thermonuclear fusion experimental reactor (ITER).
Background technology
According to current magnetically confined plasma fusion control technology development trend, the magnetic confinement fusion demonstration reactor after international thermonuclear fusion experimental reactor (ITER) will mainly adopt deuterium tritium as basic fuel.Deuterium at the content of occurring in nature compared with horn of plenty, but tritium is at occurring in nature content very rare (in atmosphere, insufficient total amount is 1 kilogram), must breed covering by the tritium of fusion reactor and realize tritium self-holding (both a tritium participates in fusion reaction and produces a neutron, and the lithium absorption that this neutron is bred in covering produces again a tritium continuation participation fusion reaction).The general covering product tritium rate (TBR) that adopts reflects whether the conceptual design of tritium propagation covering can meet the self-holding needs of fusion reactor tritium.In general the TBR of tritium propagation covering should be greater than 1, consider the loss of tritium in cyclic process and for next fusion reactor device provides enough startup tritium to realize as early as possible the scale multiplication of fusion reactor, some scholars think that the TBR of the HCSB-DEMO after ITER should be greater than 1.15.This conceptual design for fusion reactor tritium propagation covering is a very stern challenge.
Once with regard to how realizing the tritium of fusion reactor, controlling oneself and to propose multiple tritium propagation covering concept in the world, through long-term research comparison, mainly contain at present two large genuses, one class is around solid-state tritium multiplication agent, adopt the mode of the cold or water-cooled of helium, the solid-state tritium propagation covering concept that low activity ferrite/martensite (hereinafter to be referred as the RAFM) steel of take is structured material, another kind of is around liquid lithium-lead breeder, adopt single cold or two cold modes, the liquid tritium propagation covering concept that the RAFM steel of take is structured material.And China selected solid-state tritium multiplication agent/helium cold/RAFM steel tritium propagation covering concept (HCCB) and liquid lithium-lead breeder/difunctional/RAFM steel tritium breed in addition research and development of covering concept (DFLL).
Wherein, the conceptual design of the cold solid-state multiplication agent of helium (HCCB) covering adopts 2 * 6 modular design, and module size is arranged by 1/2 vertical experiment window; Tritium multiplication agent adopts the lithium ceramic bead of Li4SiO4, and neutron multiplication agent adopts beryllium metallic microspheres, is ball bed structure; Structured material adopts low activation RAFM steel; 8MPa pressure, out temperature are respectively the helium of 300 ℃ and 500 ℃ as cooling medium.Plumbous (DFLL) covering conceptual design of difunctional liquid lithium is also arranged according to 1/2 vertical experiment window, adopts low activation RAFM steel as structured material, adopts helium gas cooling structure member; During single cold pattern, liquid lithium lead is not only as multiplication agent and as cooling medium, and the plumbous flowing velocity of lithium is (<1mm/s) slowly, outlet temperature lower (～400 ℃); During two cold pattern, liquid lithium lead not only carries nuclear heat as multiplication agent but also as cooling medium, the plumbous flowing velocity of lithium fast (～10mm/s), outlet temperature higher (700 ℃).
Compare with the plumbous tritium propagation of liquid lithium covering concept, solid-state tritium propagation covering concept is more safe and reliable, does not have liquid lithium lead to bring magnetic current knowledge topic in the high-intensity magnetic field current downflow of magnetic trapped fusion apparatus.But shortcoming is also very outstanding, in HCSB-DEMO from now on, how to realize exactly the problem of reloading online.More external experts have proposed to utilize the mobility of the distinctive similar liquids of solid-state tritium propagation covering ball bed self, with carrier gas, blow bead, allow solid-state tritium multiplication agent also " flow ", thereby realize, reload.But for the conceptual design of the cold solid-state multiplication agent of the helium of current China (HCCB) covering, this mode of reloading implements more difficult, mainly due to Chinese HCCB covering conceptual design, to have adopted the concept of submodule, compare the solid-state tritium propagation cladding modular of Europe and Japan, inner structure is more complex, the flow path that causes proposing tritium carrier gas is very tortuous, and particularly Qiu Chuan district and carry between tritium carrier gas channel and adopted fence, makes the mobile of lithium ceramic bead become impossible.
From carrying tritium technical standpoint, it is all to adopt the helium that contains hydrogen to utilize isotopic displacement effect that tritium is taken out of from lithium ceramic bead (HCSB concept) or Li-Pb alloy (DFLL) as carrier gas that two kinds of current tritiums of tritium propagation cladding systems of HCCB and DFLL extract, because tritium has certain solubleness at lithium pottery and Li-Pb alloy, therefore all can there is the retention problems of tritium in these two kinds of covering concepts, therefore needs the carrier gas (more than 600 degree) of high temperature to strengthen separating out of tritium.And the tritium of being taken out of by carrier gas proposing tritium system design and need to realize helium and hydrogen isotope by low temperature (reaching liquid nitrogen temperature) selective adsorption according to order the first two concept, helium after separation reheats 500 degree again and sends above tritium breeding blanket back to and remove to carry tritium as carrier gas, from the angle of HCSB-DEMO from now on, such tritium route of carrying is very uneconomic.
For existing solid-state and problem that liquid two kinds of fusion covering tritiums propagation solution exists, we have proposed a kind of new fusion covering tritium propagation solution based on deuterium Lithia heavy aqueous solution.
Summary of the invention
The purpose of this utility model is to provide a kind of new fusion reactor blanket tritium propagation solution, to solve the self-holding problem of tritium of deuterium tritium fusion technology research device, fusion engineering experimental reactor and HCSB-DEMO after international thermonuclear fusion experimental reactor (ITER).
For achieving the above object, the technical solution of the utility model is, a kind of new fusion reactor tritium propagation cladding systems based on deuterium Lithia heavy aqueous solution, and this system comprises following characteristics:
One, this system is comprised of tritium propagation covering body, a circuit system, tritium enrichment system three parts, tritium propagation covering body is connected by fluid inlet, two mouths of pipe of fluid egress point with a circuit system, and a circuit system is connected with tritium enrichment system by the steam (vapor) outlet of its decompression vapor-liquid separating device.
Two, this system adopts the heavy water saturated solution of deuterium Lithia as tritium multiplication agent and cooling medium, according to different covering power density designs, wherein the volumetric molar concentration of deuterium Lithia is between 1-15mol/l, one circuit cools medium working temperature is between 120 ℃-550 ℃, and working pressure is between 1MPa-26MPa.
Three, one circuit systems comprise that voltage stabilizer, heat exchanger, pump, decompression vapor-liquid separating device, mixer form.The vapor-liquid separating device that wherein reduces pressure is connected with tritium enrichment system by steam (vapor) outlet.The heavy aqueous solution that contains the deuterium Lithia of tritium is realized gas-liquid separation in decompression separation device.Mixer is mainly used in supplementing deuterium Lithia heavy aqueous solution.
Four, tritium enrichment system adopts current mature heavy water reactor to put forward tritium technology, and the device combining by a multistage steam catalysis exchange and cryogenic rectification is enriched to deuterium tritium amount than the scope at 0.9-1.1 by tritium concentration.
Five, tritium propagation covering body is comprised of the first wall, lattice plate, neutron multiplication ball bed, rear plate.The first wall flux of plasma, lattice plate supports neutron multiplication ball bed implementation structure, and rear plate is realized fluid and is distributed.And all contain cooling duct in the first wall, lattice plate, rear plate, and as the deuterium Lithia heavy aqueous solution of cooling medium and tritium multiplication agent, will in pipeline, flow in order, realize tritium propagation cooling covering body.
Six, it is basic structure material that tritium propagation covering body adopts low activation ferrite/martensite steel, and optional model has domestic CLAM and CLF-1, external Eurofer and F82H; Beryllium and beryllium alloy bead that neutron multiplication ball bed is 0.05-2mm by diameter are filled, and optional beryllium alloy comprises Be 12m and Be 17m 5(M is Ti, W, and V, Ta, the metals such as Zr, the atomic percent of M element in beryllium alloy is at 5%-30%).
Its groundwork principle is as follows:
The By Fusion Neutron that the fusion reaction of deuterium tritium produces produces tritium with the contained lithium core of the deuterium Lithia generation nuclear reaction in covering, and the D atom in heavy water and deuterium Lithia also can serve as product tritium material by absorption portion By Fusion Neutron to a certain extent simultaneously.The tritium producing in covering, will be combined with deuterium oxygen element and form DTO, combine together with flow media, form containing tritium heavy aqueous solution (wherein solute is deuterium Lithia, and solvent is for forming containing tritium heavy water).By the decompression separation device in a loop, the part that contains tritium heavy aqueous solution is converted into the heavy water vapour (DTO+D containing tritium containing tritium heavy water 2and import tritium enrichment system O).
Remaining deuterium Lithia heavy aqueous solution imports heat-exchanger rig, because deuterium Lithia and lithium nuclear reaction meeting cause the loss of solute, and contain tritium heavy water, through decompression separation, can cause the loss of solvent, therefore the deuterium Lithia heavy aqueous solution through heat-exchanger rig need to pass through a mixer, supplements new deuterium Lithia heavy aqueous solution.This process has also realized online flowing and has reloaded.
Here the heavy water in the heavy water reactor that the deuterium enriched system of mentioning is applied with current scale is carried tritium device consistent (not being described further in this invention); main by multistage steam catalysis exchange and cryogenic rectification technology; tritium concentration is enriched to deuterium tritium amount ratio and approaches 1:1; for fusion reactor deuterium triton fusion reaction use, in tritium enrichment process, obtain the heavy water that tritium concentration is extremely low and can be used as the solvent use supplementing with deuterium Lithia heavy aqueous solution.
The beneficial effects of the utility model are: (1) adopts flow media simultaneously as tritium multiplication agent and cooling medium, has simplified cladding structure, is easy to the processing of covering body; (2) compare traditional solid blanket system, tritium multiplication agent has mobility, and easily realization is reloaded online; (3) compare traditional liquid blanket system, evaded the magnetic current knowledge topic that liquid metal flows and brings, the etching problem of liquid metal to structured material, the security that has improved cladding systems; (4) loop that this invention relates to and heavy water are proposed the scale application in heavy water reactor of tritium technology, and technology maturation is reliable.
Accompanying drawing explanation
Fig. 1 is the tritium propagation cladding systems schematic diagram based on deuterium Lithia heavy aqueous solution.
Fig. 2 is the tritium propagation covering body construction schematic diagram based on deuterium Lithia heavy aqueous solution.
Embodiment
Embodiment 1
The propagation of the tritium for fusion reactor engineering experiment porch cladding systems based on deuterium Lithia heavy aqueous solution as shown in Figure 1, this system is comprised of tritium propagation covering body, a circuit system, tritium enrichment system three parts, tritium propagation covering body is connected by fluid inlet, two mouths of pipe of fluid egress point with a circuit system, and a circuit system is connected with tritium enrichment system by the steam (vapor) outlet of its decompression vapor-liquid separating device.
This system adopts the heavy water saturated solution of deuterium Lithia as tritium multiplication agent and cooling medium, and wherein the volumetric molar concentration of deuterium Lithia is between 5mol/l, and tritium is bred 120 ℃ of covering body inlet temperatures, and 150 ℃ of working pressures of outlet temperature are at 1MPa.This parameter is to consider that fusion reactor engineering experiment porch is mainly used in the technical research of fusion reactor correlation engineering, without an urgent demand of fusion energy conversion, extraction, but must meet tritium, controls oneself.Adopt lower working temperature, can make covering body pipeline pressure-bearing significantly reduce, can reduce structured material consumption in design, improve the neutron economy of covering, thereby obtain the higher tritium rate of increase, meeting under the self-holding prerequisite of tritium, for further HCSB-DEMO provides, start tritium source.
One circuit system comprises that voltage stabilizer, heat exchanger, pump, decompression vapor-liquid separating device, mixer form.The vapor-liquid separating device that wherein reduces pressure is connected with tritium enrichment system by steam (vapor) outlet.The heavy aqueous solution that contains the deuterium Lithia of tritium is realized gas-liquid separation in decompression separation device.Mixer is mainly used in supplementing deuterium Lithia heavy aqueous solution.
Tritium enrichment system adopts current mature heavy water reactor to put forward tritium technology, and the cryogenic columns device combining by a multistage steam catalysis exchange and cryogenic rectification is enriched to deuterium tritium amount ratio 0.95 by tritium concentration.
As shown in Figure 2, tritium propagation covering body is comprised of the first wall 1, lattice plate 2, neutron multiplication ball bed 3, rear plate 4.Wherein in the first wall, lattice plate, rear plate, all contain cooling duct, will be mobile in order in pipeline as the deuterium Lithia heavy aqueous solution of cooling medium and tritium multiplication agent.It is basic structure material as low activation ferrite/martensite steel that tritium propagation covering body adopts CLF-1; The Be bead that neutron multiplication ball bed is 1.0mm by diameter is filled.In Fig. 2,5 is fusionplasma.
Embodiment 2
The propagation of the tritium for HCSB-DEMO cladding systems based on deuterium Lithia heavy aqueous solution, this system is comprised of tritium propagation covering body, a circuit system, tritium enrichment system three parts, tritium propagation covering body is connected by fluid inlet, two mouths of pipe of fluid egress point with a circuit system, and a circuit system is connected with tritium enrichment system by the steam (vapor) outlet of its decompression vapor-liquid separating device.
This system adopts the heavy water saturated solution of deuterium Lithia as tritium multiplication agent and cooling medium, and wherein the volumetric molar concentration of deuterium Lithia is between 5.5mol/l, and tritium is bred 260 ℃ of covering body inlet temperatures, and 280 ℃ of working pressures of outlet temperature are at 8MPa.
One circuit system comprises that voltage stabilizer, heat exchanger, pump, decompression vapor-liquid separating device, mixer form.The vapor-liquid separating device that wherein reduces pressure is connected with tritium enrichment system by steam (vapor) outlet.The heavy aqueous solution that contains the deuterium Lithia of tritium is realized gas-liquid separation in decompression separation device.Mixer is mainly used in supplementing deuterium Lithia heavy aqueous solution.
Tritium enrichment system adopts current mature heavy water reactor to put forward tritium technology, and the high temperature tower apparatus combining by a multistage steam catalysis exchange and cryogenic rectification is enriched to deuterium tritium amount ratio 0.95 by tritium concentration.
Tritium propagation covering body is comprised of the first wall, lattice plate, neutron multiplication ball bed, rear plate.Wherein in the first wall, lattice plate, rear plate, all contain cooling duct, will be mobile in order in pipeline as the deuterium Lithia heavy aqueous solution of cooling medium and tritium multiplication agent.It is basic structure material as low activation ferrite/martensite steel that tritium propagation covering body adopts CLF-1; The Be that neutron multiplication ball bed is 1.0mm by diameter 12ti bead is filled.

Claims (4)

1. the tritium based on deuterium Lithia heavy aqueous solution is bred cladding systems, it is characterized in that this system is comprised of tritium propagation covering body, a circuit system, tritium enrichment system three parts, tritium propagation covering body is connected by fluid inlet, two mouths of pipe of fluid egress point with a circuit system, and a circuit system is connected with tritium enrichment system by the steam (vapor) outlet of its decompression vapor-liquid separating device.
2. the tritium propagation cladding systems based on deuterium Lithia heavy aqueous solution as claimed in claim 1, is characterized in that a circuit system is comprised of voltage stabilizer, heat exchanger, ebullator, decompression vapor-liquid separating device, mixing feed supplementing device; The vapor-liquid separating device that wherein reduces pressure is connected with tritium enrichment system by steam (vapor) outlet, and the heavy aqueous solution that contains the deuterium Lithia of tritium is realized gas-liquid separation in decompression separation device.
3. the tritium based on deuterium Lithia heavy aqueous solution as claimed in claim 2 is bred cladding systems, it is characterized in that tritium propagation covering body is comprised of the first wall (1), lattice plate (2), neutron multiplication ball bed (3), rear plate (4), wherein the first wall (1), lattice plate (2), rear plate all contain cooling duct in (4), and flow in order in cooling duct as the deuterium Lithia heavy aqueous solution of cooling medium and tritium multiplication agent.
4. tritium based on deuterium Lithia heavy aqueous solution propagation cladding systems as claimed in claim 3, is characterized in that beryllium and beryllium alloy bead that neutron multiplication ball bed is 0.05-2mm by diameter fill.
CN201320608436.XU 2013-09-29 2013-09-29 Tritium breeding blanket system based on lithium deuteroxide heavy water solution Expired - Lifetime CN203552711U (en)

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103500588A (en) * 2013-09-29 2014-01-08 罗天勇 Tritium breeding blanket system based on lithium deuteroxide heavy water solution
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
CN108550404A (en) * 2018-04-20 2018-09-18 北京工业大学 A kind of fluidised form tritium proliferation ceramic composite

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103500588A (en) * 2013-09-29 2014-01-08 罗天勇 Tritium breeding blanket system based on lithium deuteroxide heavy water solution
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
CN108550404A (en) * 2018-04-20 2018-09-18 北京工业大学 A kind of fluidised form tritium proliferation ceramic composite

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Granted publication date: 20140416