CN109797312A - A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal - Google Patents
A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal Download PDFInfo
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- CN109797312A CN109797312A CN201910224855.5A CN201910224855A CN109797312A CN 109797312 A CN109797312 A CN 109797312A CN 201910224855 A CN201910224855 A CN 201910224855A CN 109797312 A CN109797312 A CN 109797312A
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- nuclear reactor
- heat dissipation
- shielding material
- alloy
- matrix coated
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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
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a kind of heat dissipation of matrix coated nuclear reactor and shielding material metals.According to weight percent, the ingredient of the alloy are as follows: Ge:2.0-3.0wt.%, Ga:0.5-0.8wt.%, Cd:4.0-6.0wt.%, Zn:10.0-11.0wt.%, Sn:1.5-2.0wt.%, In:0.5-0.8wt.%, Cu:0.2-0.4wt.%, surplus are lead.The material can be because the spinodal decomposition effect of liquid phase generates two different melts in process of setting, and both melts can be solidified respectively and produce the low melting point isolated area being distributed in matrix.The material of the type can be widely used in the nuclear reactor for needing to radiate, while can provide the screen effect haveing excellent performance.Process is simple, low for equipment requirements, is convenient for industrialized production and extensive use.
Description
Technical field
The present invention relates to technical field of alloy, specifically, being related to a kind of metal.
Background technique
Nuclear energy uses are the important symbols of defense force and national economy level, it is shown that a national comprehensive strength.
In energy plaque increasingly weary 21st century, nuclear power will become most important cleaning, efficient, the reliable energy.Nuclear energy uses are aobvious
Show a national comprehensive strength, be the important symbol of defense force and national economy level, therefore peace exploitation nuclear energy is various countries
Pay attention to extensively.
Nuclear reactor will release very big heat in course of normal operation, but only therein 30% or so can be turned
It is changed to the energy (including mechanical energy) of other forms.Remaining heat will be discharged in the form of waste heat, thus nuclear reactor needs
Many water are cooled down.That is, to maintain many security systems and shielding harness during working normally with reactor
Normal work.In addition, also to guarantee waste heat can normal discharge system, form normal Natural Circulation.If heat dissipation
To take heat in heap out of, the temperature and pressure in heap will slowly rise scarce capacity, after the long period, coolant in heap
It is possible that can boil, pressure also can be more than safe limit value, the safety of final Threat Reaction heap.Thus, the efficient of reactor dissipates
Heat is always nuclear industry field and its important direction.
When reactor operation, nuclear fission reaction will generate a large amount of neutrons and gamma-rays, and fission product decay also releases
α, β particle and gamma-rays.α and β particle range is very short, it is easy to be absorbed by air or other objects, generally not to operator
It constitutes a threat to.Neutron and gamma-rays have extremely strong penetration capacity.In order to stop them to require that guard shield is arranged in reactor surrounding
Layer protection staff and equipment are injured from radioactive ray.The material that shielding fast neutron need to select light element to form, shielding gamma-rays is then
The material that heavy element need to be selected to form, therefore heap external shielding layer often uses and the co-ordinative construction of the element containing weight.
Currently, due to acting on that national economy field is more and more prominent to nuclear power generation, so that the heat dissipation of nuclear reactor is got over
To be more taken seriously.Various countries have put into a large amount of man power and material and have conducted in-depth research and industrialization, and developed country is special
Not the U.S., Japan and Russia waited formd scale nuclear reactor heat dissipation industry, be able to produce it is multi-class and
The normalization product of series.This patent provides a kind of for nuclear reactor field heat transmission lead from the angle of materialogy
Material and its operational version.
Summary of the invention
The purpose of the present invention is to overcome the deficiency in the prior art, provides a kind of heat dissipation of matrix coated nuclear reactor and shielding
Material metal.The material has excellent thermal response ability and radiating efficiency between 150-250 degree.This method also has
The characteristics of production cost is low, is convenient for large-scale production.
To achieve the goals above, the present invention adopts the following technical scheme:
A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal；According to weight percent, the ingredient of the alloy
Are as follows: Ge:2.0-3.0wt.%, Ga:0.5-0.8wt.%, Cd:4.0-6.0wt.%, Zn:10.0-11.0wt.%, Sn:1.5-
2.0wt.%, In:0.5-0.8wt.%, Cu:0.2-0.4wt.%, surplus are lead.
The preparation method of above-mentioned heat sink material is comprised the following steps that alloy according to required ingredient with postponing, is put into
Melting is carried out in induction furnace, and is protected using graphite crucible and argon gas；10 minutes are kept the temperature in 400-450 degree to fill using electromagnetic agitation
Divide alloy melt after mixing evenly, imports in graphite jig and cast.Ingot casting is subjected to cold rolling, the pressure rolled per pass
Amount is 10-20%;It will be in the recrystallization annealing of 100-120 degree 1 hour of progress between every three passage;It so repeats to be rolled down to institute
The thickness needed (generally between 0.1-5mm).
Compared with prior art, the invention has the following beneficial effects:
(1) this patent provides one kind and imitates as nuclear reactor and hot channel centre for pointing to improve heat dissipation
The solution of rate.The material structure is as shown in Figure 1, include matrix part A and package phase part B.Wherein two parts A and B
It is that the liquid phases of two kinds of heterogeneities is decomposed into during solidification since spinodal decomposition effect can occur for the liquid phase of the alloy,
Simultaneously because the liquid phase of two kinds of heterogeneities solidify respectively obtained from body portion and package phase part.The material can be used for
The heat dissipation of nuclear reactor field, principle are the material to be placed on to nuclear reactor hair component (fever end) and hot channel is (scattered
Hot end) gap in, when hot-fluid from fever end flow through the boundary material when, due to wrap up mutually have low fusing point and most
First melt.This effect can make entire material softening, can effectively fill fever end and heat dissipation at the working temperature
The gap at end and make the job security of nuclear reactor have bigger guarantee.
(2) fusion temperature of the material matrix is 200-250 degree, and the fusion temperature for wrapping up phase is 160-170 degree.Entirely
The entirety of material can obtain high heat transfer coefficient (30-50W/m ﹒ K), thus this matrix passes through the spinodal decomposition effect of liquid phase
The method of package low melting point phase is a big innovation in field of radiating.This design method can fundamentally prevent low melting point phase
Leakage is so as to cause gap increase, the unfavorable result that heat dissipation effect deteriorates.
(3) due to being lead-containing alloy, which can also play very outstanding screen for the thermally conductive outer of nuclear reactor
Cover the effect of material.Effectively attenuation ray can be thus used to, play shielding action, ensure nuclear reactor system and environment peace
Entirely.In addition, the material is also used as safety, nuclear screening material functions reliably and efficiently come make nuclear fuel and nuke rubbish transport with
The container of storage.Thus, which is used for nuclear industry field, while can not only playing raising heat transfer efficiency, can also make
The radiation product that a variety of reactors are absorbed for shielding material, has ensured the safety around nuclear reactor.
(4) the product practicability is wide, and processing smelting process is simple, and production cost is low, is convenient for industrialized large-scale production
And practical application.It is applying and after industrialization, not only can solve industry problems, while can also obtain great market value.
Detailed description of the invention
Fig. 1 is the heat sink material structural schematic diagram of present patent application, including matrix part A and package phase part B.Wherein A
Spinodal decomposition effect can occur with the liquid phase that B two are partly due to the alloy and be decomposed into during solidification two kinds it is different
The liquid phase of ingredient, simultaneously because the liquid phase of two kinds of heterogeneities solidify respectively obtained from body portion and package phase part.
Specific embodiment
Embodiment 1
A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal.According to weight percent, the ingredient of the alloy
Are as follows: Ge:2.0wt.%, Ga:0.5wt.%, Cd:4.0wt.%, Zn:10.0wt.%, Sn:1.5wt.%, In:0.5wt.%, Cu:
0.2wt.%, surplus are lead.
The preparation method of above-mentioned heat sink material is comprised the following steps that alloy according to required ingredient with postponing, is put into
Melting is carried out in induction furnace, and is protected using graphite crucible and argon gas；10 minutes are kept the temperature in 400-450 degree to fill using electromagnetic agitation
Divide alloy melt after mixing evenly, imports in graphite jig and cast.Ingot casting is subjected to cold rolling, the pressure rolled per pass
Amount is 10-20%;It will be in the recrystallization annealing of 100-120 degree 1 hour of progress between every three passage;It so repeats to be rolled down to institute
The thickness needed (generally between 0.1-5mm).
The fusion temperature of the material matrix is 230 degree, and the fusion temperature for wrapping up phase is 160 degree, and the entirety of entire material can
To obtain high heat transfer coefficient (35W/m ﹒ K).The material is placed on nuclear reactor hair component (fever end) and hot channel (dissipates
Hot end) gap in, when hot-fluid from fever end flow through the boundary material when, due to wrap up mutually have low fusing point and most
First melt.This effect can make entire material softening, can effectively fill fever end and heat dissipation at the working temperature
The gap at end and make the job security of nuclear reactor have bigger guarantee.Due to being lead-containing alloy, which is being used for
Nuclear reactor it is thermally conductive outer, very outstanding shielding material can also be played the role of.
Embodiment 2
A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal.According to weight percent, the ingredient of the alloy
Are as follows: Ge:3.0wt.%, Ga:0.8wt.%, Cd:6.0wt.%, Zn:11.0wt.%, Sn:2.0wt.%, In:0.8wt.%, Cu:
0.4wt.%, surplus are lead.
The preparation method of above-mentioned heat sink material is comprised the following steps that alloy according to required ingredient with postponing, is put into
Melting is carried out in induction furnace, and is protected using graphite crucible and argon gas；10 minutes are kept the temperature in 400-450 degree to fill using electromagnetic agitation
Divide alloy melt after mixing evenly, imports in graphite jig and cast.Ingot casting is subjected to cold rolling, the pressure rolled per pass
Amount is 10-20%;It will be in the recrystallization annealing of 100-120 degree 1 hour of progress between every three passage;It so repeats to be rolled down to institute
The thickness needed (generally between 0.1-5mm).
The fusion temperature of the material matrix is 240 degree, and the fusion temperature for wrapping up phase is 165 degree, and the entirety of entire material can
To obtain high heat transfer coefficient (40W/m ﹒ K).The material is placed on nuclear reactor hair component (fever end) and hot channel (dissipates
Hot end) gap in, when hot-fluid from fever end flow through the boundary material when, due to wrap up mutually have low fusing point and most
First melt.This effect can make entire material softening, can effectively fill fever end and heat dissipation at the working temperature
The gap at end and make the job security of nuclear reactor have bigger guarantee.Due to being lead-containing alloy, which is being used for
Nuclear reactor it is thermally conductive outer, very outstanding shielding material can also be played the role of.
Embodiment 3
A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal.According to weight percent, the ingredient of the alloy
Are as follows: Ge:2.5wt.%, Ga:0.6wt.%, Cd:4.2wt.%, Zn:10.5wt.%, Sn:1.8wt.%, In:0.6wt.%, Cu:
0.3wt.%, surplus are lead.
The preparation method of above-mentioned heat sink material is comprised the following steps that alloy according to required ingredient with postponing, is put into
Melting is carried out in induction furnace, and is protected using graphite crucible and argon gas；10 minutes are kept the temperature in 400-450 degree to fill using electromagnetic agitation
Divide alloy melt after mixing evenly, imports in graphite jig and cast.Ingot casting is subjected to cold rolling, the pressure rolled per pass
Amount is 10-20%;It will be in the recrystallization annealing of 100-120 degree 1 hour of progress between every three passage;It so repeats to be rolled down to institute
The thickness needed (generally between 0.1-5mm).
The fusion temperature of the material matrix is 230 degree, and the fusion temperature for wrapping up phase is 170 degree, and the entirety of entire material can
To obtain high heat transfer coefficient (42W/m ﹒ K).The material is placed on nuclear reactor hair component (fever end) and hot channel (dissipates
Hot end) gap in, when hot-fluid from fever end flow through the boundary material when, due to wrap up mutually have low fusing point and most
First melt.This effect can make entire material softening, can effectively fill fever end and heat dissipation at the working temperature
The gap at end and make the job security of nuclear reactor have bigger guarantee.Due to being lead-containing alloy, which is being used for
Nuclear reactor it is thermally conductive outer, very outstanding shielding material can also be played the role of.
Claims (3)
1. a kind of matrix coated nuclear reactor heat dissipation and shielding material metal；According to weight percent, the alloy at
It is divided into: Ge:2.0-3.0wt.%, Ga:0.5-0.8wt.%, Cd:4.0-6.0wt.%, Zn:10.0-11.0wt.%, Sn:1.5-
2.0wt.%, In:0.5-0.8wt.%, Cu:0.2-0.4wt.%, surplus are lead.
2. a kind of heat dissipation of matrix coated nuclear reactor described in claim 1 and shielding material metal, it is characterised in that packet
It includes following steps: by alloy according to required ingredient with postponing, being put into induction furnace and carry out melting, and use graphite crucible and argon
Gas shielded；400-450 degree keep the temperature 10 minutes using electromagnetic agitation sufficiently by alloy melt after mixing evenly, import graphite jig
Inside cast.
3. a kind of matrix coated nuclear reactor heat dissipation and shielding material metal, feature exist according to claim 1
In including following procedure of processing: ingot casting being carried out cold rolling, the drafts rolled per pass is 10-20%;It will be between every three passage
100-120 degree carries out the recrystallization annealing of 1 hour;So repeat be rolled down to required thickness (generally 0.1-5mm it
Between).
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| CN201910224855.5A CN109797312A (en) | 2019-03-24 | 2019-03-24 | A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal |
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| CN201910224855.5A CN109797312A (en) | 2019-03-24 | 2019-03-24 | A kind of heat dissipation of matrix coated nuclear reactor and shielding material metal |
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108118187A (en) * | 2018-02-01 | 2018-06-05 | 广州宇智科技有限公司 | The high-strength resistance to oxidation Pb-Li-Ge lead lithium alloys of shielding material |
| CN108179312A (en) * | 2018-02-05 | 2018-06-19 | 广州宇智科技有限公司 | Have the resistance to oxidation Pb-Li-V lead lithium alloys of high high-temp stability |
| CN108203775A (en) * | 2018-02-07 | 2018-06-26 | 广州宇智科技有限公司 | The corrosion-resistant lithium alloy of lead containing Sc with extremely low work hardening rate |
| CN108251691A (en) * | 2018-01-09 | 2018-07-06 | 安泰天龙钨钼科技有限公司 | A kind of high-purity cerrobase alloy and preparation method thereof |
| CN108251689A (en) * | 2018-02-05 | 2018-07-06 | 广州宇智科技有限公司 | Has the corrosion-resistant Pb-Li-Zr lead lithium alloy of high high-temp stability |
| CN108588479A (en) * | 2018-04-04 | 2018-09-28 | 广州宇智科技有限公司 | Austenitation heat treatment lead bath metal containing Ca and Ru |
-
2019
- 2019-03-24 CN CN201910224855.5A patent/CN109797312A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108251691A (en) * | 2018-01-09 | 2018-07-06 | 安泰天龙钨钼科技有限公司 | A kind of high-purity cerrobase alloy and preparation method thereof |
| CN108118187A (en) * | 2018-02-01 | 2018-06-05 | 广州宇智科技有限公司 | The high-strength resistance to oxidation Pb-Li-Ge lead lithium alloys of shielding material |
| CN108179312A (en) * | 2018-02-05 | 2018-06-19 | 广州宇智科技有限公司 | Have the resistance to oxidation Pb-Li-V lead lithium alloys of high high-temp stability |
| CN108251689A (en) * | 2018-02-05 | 2018-07-06 | 广州宇智科技有限公司 | Has the corrosion-resistant Pb-Li-Zr lead lithium alloy of high high-temp stability |
| CN108203775A (en) * | 2018-02-07 | 2018-06-26 | 广州宇智科技有限公司 | The corrosion-resistant lithium alloy of lead containing Sc with extremely low work hardening rate |
| CN108588479A (en) * | 2018-04-04 | 2018-09-28 | 广州宇智科技有限公司 | Austenitation heat treatment lead bath metal containing Ca and Ru |
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Application publication date: 20190524 |