CN105551530A - Fusion reactor tungsten divertor structure design based on high temperature fused salt cooling - Google Patents
Fusion reactor tungsten divertor structure design based on high temperature fused salt cooling Download PDFInfo
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- CN105551530A CN105551530A CN201510932989.4A CN201510932989A CN105551530A CN 105551530 A CN105551530 A CN 105551530A CN 201510932989 A CN201510932989 A CN 201510932989A CN 105551530 A CN105551530 A CN 105551530A
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- tungsten
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/13—First wall; Blanket; Divertor
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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 present invention discloses a fusion reactor tungsten divertor structure design based on high temperature fused salt cooling. The fusion reactor tungsten divertor structure design comprises a tungsten surface pair plasma material and tungsten and lanthanum alloy heat sinks. The tungsten and lanthanum alloy heat sinks comprises a tungsten and lanthanum alloy heat sink 1 and a tungsten and lanthanum alloy heat sink 2. The tungsten and lanthanum alloy heat sink 1 is a half pipe with a C-shaped cross section, and the tungsten and lanthanum alloy heat sink 2 is a half pipe with a round angle and a semi-rectangle-shaped cross section. The tungsten surface pair plasma material is connected to the tungsten and lanthanum alloy heat sink 1, and the tungsten and lanthanum alloy heat sink 1 is connected to the tungsten and lanthanum alloy heat sink 2 to form a whole pipe. through the effective combination of tungsten and lanthanum alloy materials and a high-temperature fused salt cooling agent, the fusion reactor tungsten divertor structure design based on high temperature fused salt cooling is provided to adapt to a fusion reactor high-flux neutron irradiation environment, the heat bearing capacity can reach a 10-20MW/m2 steady-state thermal load, the structural material neutron activation is low, the , nuclear waste processing after component retirement is relatively easy, and the improvement of fusion reactor power generation economical efficiency is facilitated.
Description
Technical field
The present invention relates to the divertor technical field of nuclear fusion device, be specifically related to a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling.
Background technology
Divertor, as one of the core component of nuclear fusion device, carries and gets rid of from the high hot-fluid of plasma and the function of particle flux.In following fusion reactor, due to the running environment of high flux neutron irradiation and the requirement of economics of power generation, divertor is necessary: (1) bears 10MW/m
2above steady state thermal load, structural strength is high; (2) structured material neutron activation degree is low, with reduce parts retired after nuclear waste disposal difficulty; (3) cooling medium running temperature is high as far as possible, to improve economics of power generation.
At present, the most ripe advanced divertor technology is tungsten copper divertor technology (being applied in EAST and ITER).Tungsten copper divertor adopts pure tungsten as plasma facing material, and this material is also the first-selected plasma facing material of fusion reactor.Pure tungsten is made into the tungsten block of square-outside and round-inside, using one deck oxygen-free copper as transition bed, is connected on the heat sink pipeline of chromium zirconium copper by the mode of high temperature insostatic pressing (HIP).In pipeline, water flowing cools divertor parts.Due to high heat conductance and the high mechanical properties of chromium zirconium copper product, under the chilled water fluid parameter with engineering feasibility (as inlet temperature 100 DEG C, flow velocity 10m/s), divertor can bear 10-20MW/m
2thermal load.Although tungsten copper divertor has the advantage of high thermal bearing capacity, it is only applicable to the device of low neutron irradiation damage (i.e. low dpa), as being about 0.44dpa after the operation in 4 years of ITER divertor.In fusion reactor, the year neutron irradiation damage estimation of measure grade at divertor position is 50dpa, can cause a large amount of activation of copper material (oxygen-free copper, chromium zirconium copper), after these parts are retired, will become reluctant height and put nuke rubbish.
In order to solve an above-mentioned difficult problem, have scholar to propose to adopt low activation steel as heat sink material, but the thermal conductivity of low activation steel is about 30W/ (mK), causes thermal bearing capacity lower than 10MW/m
2thermal load.In addition, no matter be adopt chromium zirconium copper or low activation steel as heat sink material, because material runs the restriction of warm area and water working pressure, the maximum operating temperature of chilled water is at about 330 DEG C, and this is unfavorable for the economy improving fusion reactor generating.
American-European scholar it is also proposed the cold finger-type divertor design of helium, adopts and is mixed with La
2o
3the tungsten lanthanum alloy of (proportion 1%) is as heat sink material, and high flow rate (~ 200m/s) high temperature (600 DEG C) helium, with the mode cooling-part of jet, meets 10MW/m
2thermal bearing capacity requirement.But, due to the cooling power of helium and heat-carrying capacity poor, the thermal bearing capacity of this structure is difficult to further raising, this structural design is extremely complicated simultaneously, and helium is very rare strategic resource, therefore, it is poor as the engineering feasibility of fusion reactor Divertor structure use.
Fused salt (as FLiBe) can run (500-1000 DEG C) at large-scale high-temperature area, and cooling power and heat-carrying capacity all significantly improve compared with helium.Tungsten lanthanum alloy can run by high-temperature area as heat sink material more than 600 DEG C, and neutron activation degree is low.So, make full use of the hot operation ability of pure tungsten and tungsten lanthanum alloy and the low feature of neutron activation degree, and the hot operation ability of fused salt, strong cooling power and heat-carrying capacity, divertor design is plasma facing material with pure tungsten, tungsten lanthanum alloy is heat sink material, fused salt is cooling medium, is well positioned to meet the requirement of fusion reactor.
Summary of the invention
The object of the invention is exactly the defect in order to make up prior art, provides a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling.
The present invention is achieved by the following technical solutions:
A kind of based on high-temperature molten salt cooling fusion reactor tungsten Divertor structure design, it is characterized in that: include tungsten in the face of plasma material and tungsten lanthanum alloy heat sink; Described tungsten lanthanum alloy is heat sink comprises tungsten lanthanum alloy heat sink one and tungsten lanthanum alloy heat sink two, tungsten lanthanum alloy is heat sink one is the semicanal in C type cross section, tungsten lanthanum alloy is heat sink two is the semicanal of half square-section of band fillet, tungsten is connected on tungsten lanthanum alloy heat sink in the face of plasma material, and tungsten lanthanum alloy is heat sink one to be connected on tungsten lanthanum alloy heat sink two and to form a homogeneous tube.
Described a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling, is characterized in that: be connected with high-temperature molten salt, temperature 600-650 DEG C in described tungsten lanthanum alloy is heat sink, flow velocity 8-20m/s, pressure 4-10MPa.
Described a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling, it is characterized in that: described tungsten is connected on tungsten lanthanum alloy heat sink by high temperature vacuum brazing with the form of multiple fritter in the face of plasma material, tungsten lanthanum alloy is heat sink one to be connected on tungsten lanthanum alloy heat sink two by high temperature vacuum brazing.
Advantage of the present invention is:
The present invention takes full advantage of the hot operation ability of pure tungsten and tungsten lanthanum alloy and the low feature of neutron activation degree, and the hot operation ability of fused salt, strong cooling power and heat-carrying capacity, can adapt to fusion reactor high flux neutron irradiation environment, thermal bearing capacity can reach 10-20MW/m
2steady state thermal load, the nuclear waste disposal after parts are retired is relatively easy, and is conducive to improving fusion reactor economics of power generation.
Accompanying drawing explanation
Fig. 1 is structural representation of the present invention.
Fig. 2 is the sectional view perpendicular to heat sink pipeline axial of structure of the present invention.
Embodiment
The present invention is further illustrated below in conjunction with the drawings and specific embodiments.
As shown in figure 1 and 2, a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling, include tungsten in the face of plasma material 1 and tungsten lanthanum alloy heat sink 2, tungsten lanthanum alloy is heat sink 2 comprises tungsten lanthanum alloy heat sink 1 and tungsten lanthanum alloy heat sink 24, tungsten lanthanum alloy is heat sink one 3 is the semicanal in C type cross section, and tungsten lanthanum alloy is heat sink 24 is the semicanal of half square-section of band fillet.Tungsten is connected to tungsten lanthanum alloy heat sink one 3 on the form of multiple fritter by high temperature vacuum brazing in the face of plasma material 1, is then connected to heat sink for tungsten lanthanum alloy 1 on tungsten lanthanum alloy heat sink 24 by high temperature vacuum brazing again and forms a homogeneous tube.Tungsten lanthanum alloy is heat sink is connected with high-temperature molten salt 5 to cool divertor, temperature 600-650 DEG C, flow velocity 8-20m/s, pressure 4-10MPa in 2, forms a complete fusion reactor tungsten Divertor structure based on high-temperature molten salt cooling.
Claims (3)
1. one kind based on high-temperature molten salt cooling fusion reactor tungsten Divertor structure design, it is characterized in that: include tungsten in the face of plasma material and tungsten lanthanum alloy heat sink; Described tungsten lanthanum alloy is heat sink comprises tungsten lanthanum alloy heat sink one and tungsten lanthanum alloy heat sink two, tungsten lanthanum alloy is heat sink one is the semicanal in C type cross section, tungsten lanthanum alloy is heat sink two is the semicanal of half square-section of band fillet, tungsten is connected on tungsten lanthanum alloy heat sink in the face of plasma material, and tungsten lanthanum alloy is heat sink one to be connected on tungsten lanthanum alloy heat sink two and to form a homogeneous tube.
2. a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling according to claim 1, is characterized in that: be connected with high-temperature molten salt, temperature 600-650 DEG C in described tungsten lanthanum alloy is heat sink, flow velocity 8-20m/s, pressure 4-10MPa.
3. a kind of fusion reactor tungsten Divertor structure design based on high-temperature molten salt cooling according to claim 1, it is characterized in that: described tungsten is connected on tungsten lanthanum alloy heat sink by high temperature vacuum brazing with the form of multiple fritter in the face of plasma material, tungsten lanthanum alloy is heat sink one to be connected on tungsten lanthanum alloy heat sink two by high temperature vacuum brazing.
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| CN105551530B CN105551530B (en) | 2018-06-05 |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107507651A (en) * | 2017-08-15 | 2017-12-22 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for following Tokamak Fusion Reactor |
| CN108615563A (en) * | 2018-04-02 | 2018-10-02 | 西安交通大学 | Fusion facility divertor water cooling module and its divertor cooled target harden structure of application |
| CN109887617A (en) * | 2019-03-20 | 2019-06-14 | 华中科技大学 | A kind of cold divertor module of finger-type helium and its manufacturing method |
| CN109961854A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | A kind of nuclear fusion first pars intramuralis cooling duct cooling based on jet stream |
| CN109979609A (en) * | 2019-03-14 | 2019-07-05 | 中国科学院合肥物质科学研究院 | A kind of fusion reactor divertor component with resistance tritium function |
| CN111477352A (en) * | 2020-04-22 | 2020-07-31 | 中国科学院合肥物质科学研究院 | U-shaped device for adjacent cooling channel of first wall of divertor of fusion device and assembly method thereof |
| CN112304586A (en) * | 2020-10-19 | 2021-02-02 | 中国科学院合肥物质科学研究院 | EAST divertor resistance characteristic test and purging efficiency test system and method |
| CN117038116A (en) * | 2023-09-25 | 2023-11-10 | 中国科学技术大学 | Anti-debonding divertor assembly based on tungsten and copper interface connection mode |
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107507651B (en) * | 2017-08-15 | 2019-05-31 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for Tokamak Fusion Reactor |
| CN107507651A (en) * | 2017-08-15 | 2017-12-22 | 中国科学院合肥物质科学研究院 | A kind of double cold loop Divertor structures suitable for following Tokamak Fusion Reactor |
| CN109961854B (en) * | 2017-12-25 | 2020-11-13 | 哈尔滨工业大学 | Internal cooling channel of first wall of nuclear fusion based on jet cooling |
| CN109961854A (en) * | 2017-12-25 | 2019-07-02 | 哈尔滨工业大学 | A kind of nuclear fusion first pars intramuralis cooling duct cooling based on jet stream |
| CN108615563A (en) * | 2018-04-02 | 2018-10-02 | 西安交通大学 | Fusion facility divertor water cooling module and its divertor cooled target harden structure of application |
| CN108615563B (en) * | 2018-04-02 | 2020-05-22 | 西安交通大学 | Divertor water-cooling module of fusion device and divertor cooling target plate structure applied by divertor water-cooling module |
| CN109979609A (en) * | 2019-03-14 | 2019-07-05 | 中国科学院合肥物质科学研究院 | A kind of fusion reactor divertor component with resistance tritium function |
| CN109887617A (en) * | 2019-03-20 | 2019-06-14 | 华中科技大学 | A kind of cold divertor module of finger-type helium and its manufacturing method |
| CN111477352A (en) * | 2020-04-22 | 2020-07-31 | 中国科学院合肥物质科学研究院 | U-shaped device for adjacent cooling channel of first wall of divertor of fusion device and assembly method thereof |
| CN112304586A (en) * | 2020-10-19 | 2021-02-02 | 中国科学院合肥物质科学研究院 | EAST divertor resistance characteristic test and purging efficiency test system and method |
| CN112304586B (en) * | 2020-10-19 | 2023-03-14 | 中国科学院合肥物质科学研究院 | EAST divertor resistance characteristic test and purging efficiency test system and method |
| CN117038116A (en) * | 2023-09-25 | 2023-11-10 | 中国科学技术大学 | Anti-debonding divertor assembly based on tungsten and copper interface connection mode |
| CN117038116B (en) * | 2023-09-25 | 2024-02-06 | 中国科学技术大学 | Anti-debonding divertor assembly based on tungsten and copper interface connection mode |
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| CN105551530B (en) | 2018-06-05 |
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