CN106544547A - A kind of nuclear field radioactive liquid waste process corrosion resistant material and preparation method thereof - Google Patents
A kind of nuclear field radioactive liquid waste process corrosion resistant material and preparation method thereof Download PDFInfo
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- CN106544547A CN106544547A CN201610967381.XA CN201610967381A CN106544547A CN 106544547 A CN106544547 A CN 106544547A CN 201610967381 A CN201610967381 A CN 201610967381A CN 106544547 A CN106544547 A CN 106544547A
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C19/00—Alloys based on nickel or cobalt
- C22C19/03—Alloys based on nickel or cobalt based on nickel
- C22C19/05—Alloys based on nickel or cobalt based on nickel with chromium
- C22C19/051—Alloys based on nickel or cobalt based on nickel with chromium and Mo or W
- C22C19/053—Alloys based on nickel or cobalt based on nickel with chromium and Mo or W with the maximum Cr content being at least 30% but less than 40%
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C19/00—Alloys based on nickel or cobalt
- C22C19/03—Alloys based on nickel or cobalt based on nickel
- C22C19/05—Alloys based on nickel or cobalt based on nickel with chromium
- C22C19/051—Alloys based on nickel or cobalt based on nickel with chromium and Mo or W
- C22C19/055—Alloys based on nickel or cobalt based on nickel with chromium and Mo or W with the maximum Cr content being at least 20% but less than 30%
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/10—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of nickel or cobalt or alloys based thereon
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Abstract
A kind of nuclear field radioactive liquid waste process corrosion resistant material of the present invention and preparation method thereof, is related to a kind of nuclear field liquid waste processing evaporator material, and the mass percent of its each component is：Cr：27.0～31.0%；Mo：3.0～5.0%；C：≤ 0.02%；P：≤ 0.01%；S：≤ 0.01%；Si：≤ 0.5%；Ti：≤ 0.10%；Al：≤ 0.04%；Cu：≤ 0.01%；Co:≤ 0.01%；Remaining is Ni.The material has excellent resistance to corrosion in nuclear field waste liquid environment, the replacement frequency of tankage can be greatly reduced, improve safety, stability and economy that radioactive liquid waste is processed, ensure evaporating concentration process safety, production capacity and efficiency are improved, the material of the present invention can greatly improve safety guarantee.
Description
Technical field
The present invention relates to a kind of anti-corrosive alloy material, specifically a kind of nuclear field radioactive liquid waste process vaporizer
Material and preparation method.
Background technology
The process of nuclear field waste liquid is all one ring of key in nuclear industry all the time, is related to environment and to human health
Material impact, paid attention to by industry circle and general public.At present in actual production process, the composition of typical radioactive liquid waste
For：HNO36mol/L, MoO3 -10mmol/L, MnO3 -10mmol/L, F-300mg/L,Zr4+300mg/L.Radioactive liquid waste needs to steam
10 times or so of concentration is sent out to reclaim nitric acid, it is important that reducing waste liquid volume, glass solidification and cement solidification is then carried out respectively.One
Since straight, nuclear field liquid waste processing material typically adopts Stainless steel 316 L, but the use of such material have one it is very big the drawbacks of,
It is required to change every 1-2, must changes less than 1 year in the case of utilization rate height.Trace it to its cause, be primarily due to
In the waste liquid of the specific composition environment, the corrosion rate of active service stainless steel material is too fast, with the development of nuclear industry, usage frequency
More and more higher, changes speed also higher, it is impossible to meet the corresponding research and production demand of nuclear industry.Accordingly, it would be desirable to upgrading of regenerating
The new evaporator material with more high-corrosion resistance, meets the application requirement of the corresponding technological process of nuclear industry, equally
Under high frequency service condition, replacement frequency is largely reduced.
Therefore, the decay resistance in specific nuclear field waste liquid environment, and preparation easy to process are greatly improved, exploitation rises
Level nuclear field liquid waste processing of new generation is significant with evaporator material.
The content of the invention
It is an object of the invention to provide a kind of nuclear field liquid waste processing evaporator material and preparation method, the material is in nuclear field
There is in waste liquid environment excellent resistance to corrosion, the replacement frequency of tankage can be greatly reduced, improve Spent Radioactive
Safety, stability and economy that liquid is processed, ensure evaporating concentration process safety, improve production capacity and efficiency, the present invention
Material can greatly improve safety guarantee.
For achieving the above object, the technical solution used in the present invention is：
Nuclear field liquid waste processing evaporator material, it is characterised in that the mass percent of each component is：
Cr：27.0～31.0%；Mo：3.0～5.0%；C：≤ 0.02%；P：≤ 0.01%；S：≤ 0.01%；Si：≤
0.5%；Ti：≤ 0.10%；Al：≤ 0.04%；Cu：≤ 0.01%；Co:≤ 0.005%；Remaining is Ni.
Above-mentioned material, preferable technical scheme are that the mass percent of each component is：
Cr：29.5～30.2%；Mo：3.5～4.7%；C：0.01%；P：0.002～0.003%；S：0.002～
0.003%；Si：0.10～0.23%；Ti：0.01～0.02%；Al：0.01～0.03%；Cu：0.001%；Co:
0.005%；
Remaining is Ni.
The preparation method of above-mentioned nuclear field liquid waste processing evaporator material, has following steps：
1) melting：Above-mentioned component is taken, is mixed, melting under vacuum, 1500 DEG C～1550 DEG C of refine, refining period vacuum>
1Pa, 1450 DEG C～1480 DEG C of pouring temperature, obtains vacuum ingot, then with ternary slag system 50%CaF2+ 20%Al2O3+ 30%CaO
(being mass percent) protects electroslag remelting, obtains the more smooth ESR ingot of surface quality；
2) Homogenization Treatments：Step 1) ESR ingot homogenization heat treatment 4～6 hours at 1100～1150 DEG C；
3) forge：1100～1150 DEG C of initial temperature of forging, final forging temperature are not less than 980 DEG C, forge slab or bar stock；
4) hot rolling：Forging stock is heated to into 1100～1150 DEG C, sheet material or Φ 12mm of the hot rolling into thickness 8mm～20mm
～Φ 20mm bars, are air cooled to room temperature；
5) it is cold rolling cold drawn：By bar plate cold rolling into cold-reduced sheet with materials, gauge thickness × fabric width be δ (1～3) mm × (150～
400) mm, centre is made annealing treatment.
Step 5) it is cold rolling cold drawn when, using (1010 DEG C～1050) DEG C × (25～60) min annealings, eliminate processing hard
Change.
Above-mentioned nuclear field radioactive liquid waste process evaporator material can be used to prepare the various containers of nuclear field liquid waste processing.
The effect of material each element of the present invention is as follows,
Ni：Matrix element, with excellent corrosion resisting property, the alloy based on nickel has intensity height, plasticity and toughness good, can
With hot and cold deformation and processing and forming, many good combination properties such as weldability is good.
Cr：Chromium is a kind of antioxidative element, is the substantially anti-corrosion element in the radioactive liquid waste environment, while and shape
Into the basic solid solution element of nickel chromium triangle solid solution, chromium promotes Nickel-based Corrosion-resistance Materials to form surface passivated membrane in an oxygen-containing environment, resists
Homogeneous corrosion has effect well.
Mo：Anti- anti-corrosion effects of the Mo to reproducibility acid is obvious, can improve corrosion resistance of the corrosion resistant alloy in reproducibility acid, right
Anti- homogeneous corrosion, intercrystalline corrosion etc. have preferably effect, and the liter high corrosion resistance in certain limit with content is improved, but is contained
Amount can excessively reduce the machinability of steel.The mass percent of molybdenum content is 3.0%～5.0%.
Al：Harmful element in abros, can increase the depth of Intergranular stress corrosion cracking, especially work as content
In 0.05%～0.14% scope, content is higher, and corrosion cracking is more serious, therefore control is below 0.04%.
Ti：Micro Ti has certain effect to melt deoxidation in melting middle and late stage, and the compound of formation can be risen to crystal boundary
To pinning effect, but Ti height may cause metallurgy to be mingled with, and control below 0.04% as impurity element herein.
Si：Silicon is beneficial under high corrosion current potential, but forms the position of field trash and easily produces spot corrosion, affects alloy
Corrosion resisting property.Therefore, Si contents are controlled below 0.5%.
S、P：The two has a strong impact on the processing characteristics of alloy, and the performance of welding performance especially welding heat affected zone can be made
Into serious infringement.The content of S, P is controlled below 0.01%.
C：Carbon content rising is very big to the performance impact of welding heat affected zone, and the carbide of formation will affect seam organization
Mechanical property, corrosion resisting property, cause welding degenerate, carbon content general control is below 0.02%.
Cu、Co：Waste liquid will cause solute atoms after having certain radiation property, Cu elements aging under long-term radiation environment
Precipitation, so as to cause material embrittlement；Co units have the longer half-life.Therefore, Cu≤0.01%, Co≤0.01%.
In preparation technology, the formulation and effect of special parameter is as follows：
For alloy ESR ingot, using Homogenization Treatments, it is therefore intended that improve Mo therein and microelement Ti, Al etc. and exist
Distributing homogeneity therein, reduction Mo elements can the trace element formation field trash such as the transgranular segregation of crystal boundary, reduction Ti, Al
Can property, simultaneously because solid solution element is less, homogenization temperature at 1100～1150 DEG C, thus reducing material in hot-working
During fracture, roll the generation of situations such as splitting, improve the lumber recovery of material.
Hot rolling is the necessary process meanses for obtaining the various final product forms of the material, provides necessary for follow-up cold machining process
Middle transition material forms, such as slab, bar stock.
It is cold rolling it is cold drawn be for the finished material for obtaining multi-form, sheet material be for the surrounding structure for preparing container, and
Wire rod is then to prepare corresponding pulling structure in container.
Annealing is, in order to eliminate the machining stress during cold working, allow anneal of material to recrystallize which, to improve material
The plasticity toughness of material, it is ensured that the cold worked smooth extension of material.
Material corrosion resistance of the present invention is greatly improved, and other performance will not be prepared to material increases larger difficulty
Degree, will not also increase processability, the weldability of difficulty of processing, i.e. material etc. excellent in the manufacturing process of vaporizer.
Nuclear field liquid waste processing evaporator material of the present invention can be plate with materials, wire rod or section bar.
Specific embodiment
Embodiment 1
The percentage by weight of nuclear field radioactive liquid waste process corrosion resistant material each component is shown in Table 1.
1 nuclear field radioactive liquid waste of table process evaporator material chemical composition (wt%)
Embodiment 2
Each component is taken according to table 1, nuclear field liquid waste processing evaporator material of the present invention is obtained with following method.
Nuclear field liquid waste processing of the present invention corrosion resisting alloy adopts vacuum induction furnace smelting and electroslag furnace refine, forged,
The operation such as hot rolling, heat treatment, cold rolling, is processed into the anti-corrosive alloy material of different product form, and processing and heat treatment process are such as
Under：
Melting：Using vacuum induction smelt and electroslag furnace remelting refining, vacuum induction smelt when 1500 DEG C of refining temperature～
1550 DEG C, refining period vacuum is better than 2Pa, and 1450 DEG C～1480 DEG C of pouring temperature obtains vacuum ingot, then protects electroslag with slag system
Remelting, obtains the more smooth ESR ingot of surface quality；Homogenization Treatments：Heat treatment 4～6 hours at 1100～1180 DEG C, so
Hammer cogging afterwards；Forging：1150～1180 DEG C of initial temperature of forging, final forging temperature is not less than 980 DEG C, can be swaged into breaking down on request
Slab or bar stock；Hot rolling：Forging stock is heated to into 1150～1180 DEG C, sheet material or Φ of the hot rolling into thickness 8mm～20mm
12mm～Φ 20mm bars, are air cooled to room temperature；It is cold rolling cold drawn：By bar plate cold rolling into required specification cold-reduced sheet with materials, by bar
The cold drawn wire rod into required specification, in cold rolling cold drawing process, can carry out 1050 DEG C × (25～60) min annealing eliminations and add
Work is hardened.
Chemical composition ranges according to set by the present invention, the melting on vaccum sensitive stove obtain three stove corrosion resistant alloy materials,
The corrosion resistant alloy material of desired form is obtained Jing after electroslag remelting, forging, rolling, drawing.
3 experimental result of embodiment
1. the performance test of material
The drilling cuttings sampling on ESR ingot of chemical composition sample, remaining all test sample are sampled along machine direction, are measured
Chemical composition as shown in table 1, mechanical property is as shown in table 2.
Radioactive liquid waste prepared by table 2 is processed and uses anti-corrosive alloy material mechanical property
2. the environmental experiment of material
Above-described embodiment material, needs to use according to the use temperature range of room temperature to 110 DEG C, and the vaporizer course of processing
To welding procedure, through simulating the corrosion-resistant experimental verification of nuclear field waste liquid environment, its decay resistance is outstanding, year corrosion rate such as table
Shown in 3.
The decay resistance of material prepared by table 3 in nuclear field waste liquid environment
Claims (6)
1. a kind of nuclear field liquid waste processing evaporator material, it is characterised in that the mass percent of each component is：
Cr：27.0～31.0%%
Mo：3.0～5.0%；
C：≤ 0.02%；P：≤ 0.01%；S：≤ 0.01%；Si：≤ 0.5%；
Ti：≤ 0.10%；Al：≤ 0.04%；Cu：≤ 0.01%；Co:≤ 0.01%；
Remaining is Ni.
2. material according to claim 1, it is characterised in that the mass percent of each component is：
3. the method for preparing the arbitrary described nuclear field liquid waste processing evaporator material of claim 1-2, it is characterised in that the party
Method has following steps：
1) melting：The component described in claim 1 or 2 is taken, is mixed, melting under vacuum, 1500 DEG C～1550 DEG C of refine, refining period
Vacuum>1Pa, 1450 DEG C～1480 DEG C of pouring temperature, obtains vacuum ingot, then protects electroslag remelting with ternary slag system, obtains table
The more smooth ESR ingot of face quality；
2) Homogenization Treatments：Step 1) ESR ingot homogenization heat treatment 4～6 hours at 1100～1180 DEG C；
3) forge：1150～1180 DEG C of initial temperature of forging, final forging temperature are not less than 980 DEG C, forge slab；
4) hot rolling：Forging stock is heated to into 1150～1180 DEG C, sheet material or Φ 12mm～Φ of the hot rolling into thickness 8mm～20mm
20mm bars, are air cooled to room temperature；
5) it is cold rolling cold drawn：By bar plate cold rolling into cold-reduced sheet with materials, gauge thickness × fabric width is δ (1～3) mm × (150～400)
mm；
6) annealing heat-treats temperature：1050 DEG C × (25～60) minute.
4. method is obtained according to claim 3, it is characterised in that：Step 1) described in ternary slag system for mass percent be
50%CaF2+ 20%Al2O3+ 30%CaO.
5. method is obtained according to claim 3, it is characterised in that：Step 5) it is cold rolling cold drawn when, using 1010 DEG C～1050
DEG C annealing eliminate processing hardening.
6. the arbitrary nuclear field radioactive liquid waste process evaporator material of claim 1～2 is preparing nuclear field liquid waste processing appearance
Apply in device.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111607721A (en) * | 2020-05-19 | 2020-09-01 | 金川集团股份有限公司 | Preparation method of GH4169A alloy strip for nuclear power |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59229457A (en) * | 1983-06-13 | 1984-12-22 | Sumitomo Metal Ind Ltd | Ni-base high-cr alloy having excellent resistance to stress corrosion cracking |
| JPH09194973A (en) * | 1996-01-10 | 1997-07-29 | Mitsubishi Heavy Ind Ltd | Sulfuric acid corrosion resistant material |
| CN101305107A (en) * | 2005-08-25 | 2008-11-12 | 溶剂热结晶成长技术研究组合 | Nickel-base corrosion-resistant alloy and corrosion-resistant members made of the alloy for the apparatus for reaction with supercritical ammonia |
| CN101978082A (en) * | 2008-03-25 | 2011-02-16 | 住友金属工业株式会社 | Nickel-based alloy |
| US20110240715A1 (en) * | 2010-03-31 | 2011-10-06 | Ge-Hitachi Nuclear Energy Americas Llc | Welding process and corrosion-resistant filler alloy and consumables therefor |
| CN104404306A (en) * | 2014-09-03 | 2015-03-11 | 上海大学 | High-strength cube texture nickel base alloy baseband for coated conductors and preparation method thereof |
-
2016
- 2016-10-31 CN CN201610967381.XA patent/CN106544547B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59229457A (en) * | 1983-06-13 | 1984-12-22 | Sumitomo Metal Ind Ltd | Ni-base high-cr alloy having excellent resistance to stress corrosion cracking |
| JPH09194973A (en) * | 1996-01-10 | 1997-07-29 | Mitsubishi Heavy Ind Ltd | Sulfuric acid corrosion resistant material |
| CN101305107A (en) * | 2005-08-25 | 2008-11-12 | 溶剂热结晶成长技术研究组合 | Nickel-base corrosion-resistant alloy and corrosion-resistant members made of the alloy for the apparatus for reaction with supercritical ammonia |
| CN101978082A (en) * | 2008-03-25 | 2011-02-16 | 住友金属工业株式会社 | Nickel-based alloy |
| US20110240715A1 (en) * | 2010-03-31 | 2011-10-06 | Ge-Hitachi Nuclear Energy Americas Llc | Welding process and corrosion-resistant filler alloy and consumables therefor |
| CN104404306A (en) * | 2014-09-03 | 2015-03-11 | 上海大学 | High-strength cube texture nickel base alloy baseband for coated conductors and preparation method thereof |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111607721A (en) * | 2020-05-19 | 2020-09-01 | 金川集团股份有限公司 | Preparation method of GH4169A alloy strip for nuclear power |
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