CN104164539A - Laser treatment method for raising stress corrosion resistance and abrasive resistance of nuclear power 690 alloy - Google Patents
Laser treatment method for raising stress corrosion resistance and abrasive resistance of nuclear power 690 alloy Download PDFInfo
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- CN104164539A CN104164539A CN201410361414.7A CN201410361414A CN104164539A CN 104164539 A CN104164539 A CN 104164539A CN 201410361414 A CN201410361414 A CN 201410361414A CN 104164539 A CN104164539 A CN 104164539A
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Abstract
The invention relates to a laser treatment method for raising stress corrosion resistance and abrasive resistance of nuclear power 690 alloy. According to the invention, a continuous laser thermal source with the wavelength of 800-1070nm is adopted to carry out a melting treatment on the cylindrical surface of a 690 alloy heat-transfer pipe while a nitrogen-assisted nitriding treatment is carried out. Laser power is 300-1000 W; laser scanning linear velocity is 200-800 mm/min; spot diameter is 0.5-3 mm; and overlap rate is 20-60%. When the nitrogen-assisted nitriding treatment is carried out while laser melting of the cylindrical surface of the 690 alloy pipe, flow rate of nitrogen is 20-30L/min; the distance from a nitrogen nozzle to the surface of the heat-transfer pipe is 5-12 mm; nitrogen pressure at an nozzle outlet is 0.5-1 MPa; and argon with auxiliary flow rate of 20-30L/min in a bore of the 690 heat-transfer pipe is used to protect the surface of the bore and cool the pipe wall. Laser melting is adopted and nitrogen is blown to a melting zone to carry out the nitriding treatment on the surface of the 690 alloy heat-transfer pipe. Thus, a compact nitriding layer with the thickness of 20-100 microns is obtained, so as to raise stress corrosion resistance and abrasive resistance.
Description
Technical field
The present invention relates to a kind of laser processing method that improves nuclear power 690 alloy stress corrosion resistance and wear resistance, belong to Materialbearbeitung mit Laserlicht field.
Background technology
With respect to traditional thermoelectricity, water power equal energy source system, nuclear power, as a kind of safe, clean, economic novel energy, plays not replaceable effect to the mankind's energy resource supply.The area of pressurized water reactor nuclear power station steam generator heat-transfer pipe accounts for 80% left and right of a loop pressure-bearing boundary area, heat-transfer pipe wall thickness is generally 1mm～1.2mm, it is the weakest part in a whole circuit pressure border, abroad service experience shows, about 30%～40% pressurized-water reactor affects and normally moves, reduces Power operation or be forced to shutdown because of steam generator heat-transfer pipe damage.The breakage of heat-transfer pipe is caused by all kinds of corrosion, comprises spot corrosion (Pitting), intergranular corrosion (IGA) and intergranular stress corrosion (IGSCC), and wherein, 60% problem belongs to stress corrosion problem.When pressurized-water reactor nuclear power plant is normally worked simultaneously, because stream causes heat-transfer pipe and the liner plate generation fretting wear that vibration causes, also increased the tendency of heat-transfer pipe corrosion cracking.
Inconel690 alloy is high Cr nickel-base alloy, is mainly used in corrosive water medium and high temperature air media environment, and has high strength, good smelting stability and good manufacturing characteristics, is widely used on nuclear power station steam generator heat-transfer pipe.But up to the present,, employing 690TT the earliest also only less than the history of 30 years, and has also had the heat-transfer pipe of a small amount of this material to occur stress corrosion crack problem and fretting wear problem as the vapour generator operation of heat transfer tubing abroad.Therefore therefore solving broken the running affairs of vapour generator is to be related to the security of Nuclear power plants and to make Nuclear power plants have the key issue of competitive and vitality.
In to the retrieval of existing patent, found the patent of invention (patent No. 101974773A of " a kind of method of the Inconel690 of raising alloy heat-transfer pipe stress corrosion resistant ability " by name, hereinafter referred to as " contrast patent "), the method that this invention adopts electrodeposited chromium to add laser irradiation is carried out surface modification.But the electrodeposited chromium technique that this patent adopts, its chromium coating easily comes off, and in electroplating process easily to environment, and the separated transportation cost that also increased of electrodeposited chromium and laser processing, is unfavorable for site disposal.
Summary of the invention
Object of the present invention is exactly in order to solve heat-transfer pipe stress corrosion crack and fretting wear problem, a kind of method that improves nuclear power 690 alloy heat-transfer pipe stress corrosion resistances and wear resistance is provided, and it can make ability and the wear resisting property of heat-transfer pipe opposing stress corrosion be largely increased.
For achieving the above object, the present invention adopts following technical scheme:
A kind of laser processing method that improves nuclear power 690 alloy stress corrosion resistance and wear resistance, when it is characterized in that adopting wavelength to be 800-1070nm continuous laser thermal source remelting 690 alloy heat-transfer pipe outer round surface, auxiliary nitrogen carries out nitriding processing, , laser power 300-1000W, laser scanning linear velocity is 200-800mm/min, spot diameter 0.5-3mm, overlapping rate 20-60%, in the time of laser melting 690 compo pipe outer round surface, auxiliary nitrogen carries out nitriding processing, nitrogen flow is 20-30L/min, nitrogen nozzle is 5-12mm to the distance of tube surface, jet exit nitrogen pressure is 0.5-1MPa, the argon gas that 690 heat-transfer pipe endoporus auxiliary flow are 20-30L/min is protected bore surface and cooling tube wall.
Obtaining thickness is the fine and close nitrided case of 20-100 μ m, and hardness is brought up to HV200-400.
This technique comprises step specific as follows:
1.Inconel690 alloy tube surface adopts alcohol to clean in advance, removes surface impurity.
2. heat-transfer pipe is fixed on lathe turntable, turntable carries out laser melting to 690 alloy tube surface when rotating, and to consolidation district, logical high pure nitrogen carries out nitriding processing with nozzle.
3. nitriding is processed simultaneously and is equipped with pure argon protection in heat-transfer pipe, prevents that heat affected zone alloy is oxidized.
Laser melting nitriding (Laser Melting and Nitriding, LMN) parameter is as follows:
Laser apparatus is semi-conductor or optical fiber laser, optical maser wavelength 800-1070nm
Laser power 300-1000W
Laser scanning speed 200-800mm/min
Spot diameter 0.5-3mm
Overlapping rate 20-60%
The nitrogen pressure 0.5-1MPa of nozzle place
Nitrogen flow is 20-30L/min
Argon flow amount is 20-30L/min
Nitrogen nozzle is 5-12mm to the distance of tube surface
The invention has the beneficial effects as follows: by the inventive method, can carry out surface treatment to more elongated pressurized water reactor nuclear power station steam generator heat-transfer pipe, and the laser nitrided case compact structure, the homogeneous microstructure that obtain, its stress corrosion resistance and wear resistance significantly improve, and the nitriding of employing short wavelength laser, light can be more effective by Matrix absorption, improves nitriding efficiency.
Accompanying drawing explanation
Fig. 1 is laser melting nitriding schematic diagram
1,690 heat-transfer pipe outside surfaces; 2, lathe turntable; 3, laser system; 4, nitriding nozzle; 5, argon gas nozzle (engaging with heat-transfer pipe inner wall sealing); 6, nitride layer; 7, heat-transfer pipe inwall; 8, consolidation district; 9, heat affected zone
Polishing scratch depth map under Fig. 2 different loads
Embodiment
Embodiment 1:
Described laser melting nitriding process is: (external diameter is 19mm to choose Inconel690 alloy heat-transfer pipe, wall thickness is 1.2mm, long 300mm), heat-transfer pipe outside surface 1 adopts alcohol to clean to remove surface impurity, and heat-transfer pipe is fixed on lathe turntable 2, turntable rotating speed is set, make the rotational line speed of 690 alloy heat-transfer pipe cylindricals reach 200mm/min, adopt wavelength is that the optical fiber laser of 1070nm carries out surface treatment simultaneously, 3 pairs of 690 alloy tube surface of laser thermal source are carried out consolidation, laser output power is 300W, spot diameter after focusing is 0.5mm, scanning overlapping rate is 20%, the nitriding nozzle 4 that is fixed on laser system periphery be take the flow of 20L/min and is sent into the high pure nitrogen (99.995%) that top hole pressure is 0.5MPa to laser irradiation region, the distance of nitriding nozzle distance tube surface is 12mm, by the argon gas nozzle 5 that connects heat-transfer pipe inwall, to passing into pure argon (99.95%) with 20L/min in heat-transfer pipe, protected simultaneously, cooling, prevent that heat-transfer pipe is oxidized.
Intercepting part sample, the mean thickness that records consolidation nitrided case 6 with microscopic examination is about 20 μ m, and recording outside surface hardness is HV200.
Intercepting 42mm nitriding pipe is made tension specimen, carries out stress corrosion tension test, and test strain rate is 1 * 10
-6s
-1, test(ing) medium 50%NaOH+0.3%SiO
2+ 0.3%Na
2s
2o
3(massfraction composition) solution.Test-results is as following table:
In table: δ---the unit elongation of sample
The relative reduction in area of RA---sample
CGR---SCC crack growth rate
I---SCC susceptibility index (stress-strain curve integral area)
UTS---maximum stress
1) intercepting 20mm laser melting nitriding pipe carries out fretting wear test
A. experimental installation: PLINT fretting apparatus;
B. friction pair: 1Cr13 stainless steel solid right cylinder (Φ 10mm * 20mm), surface roughness Ra=0.02 μ m;
C. test parameter: normal load is respectively F
n=20,50,80N, cycle index 20000 times, displacement amplitude 100 μ m, frequency 2Hz, normal temperature and pressure;
D. test-results is as Fig. 2.
Embodiment 2:
Described laser melting nitriding process is: consolidation nitriding pre-treatment is with embodiment 1, adopt the semiconductor laser that wavelength is 980nm to carry out surface treatment, semiconductor laser output rating is 600W, heat-transfer pipe external circe speed is 500mm/min, spot diameter is 1.5mm, scanning overlapping rate is 40%, the nitriding nozzle that is fixed on laser system periphery is sent into the high pure nitrogen (99.995%) of 25L/min to laser irradiation region, the distance of nozzle distance tube surface is 9mm, nitrogen outlet pressure is 0.75MPa, by the argon gas nozzle that connects heat-transfer pipe inwall, to passing into 25L/min pure argon (99.95%) in heat-transfer pipe, protected simultaneously, cooling.
Intercepting part sample, records consolidation nitrided case mean thickness with microscopic examination and is about 72 μ m, and recording outside surface hardness is HV280.
Intercepting 42mm nitriding pipe is made tension specimen, carries out stress corrosion tension test, and test parameter is with embodiment 1, and test-results is as following table:
1) intercepting 20mm laser melting nitriding pipe carries out fretting wear test
Fretting wear test parameter is with embodiment 1, and test-results is as Fig. 2.
Embodiment 3:
Described laser melting nitriding process is: consolidation nitriding pre-treatment is with embodiment 1, adopt the semiconductor laser that wavelength is 800nm to carry out surface treatment, laser output power is 1000W, heat-transfer pipe external circe speed is 800mm/min, spot diameter is 3mm, scanning overlapping rate is 60%, the nozzle that is fixed on laser system periphery is sent into 30L/min high pure nitrogen (99.995%) to laser irradiation region, the distance of nozzle distance tube surface is 5mm, nitrogen outlet pressure is 1MPa, by the argon gas nozzle that connects heat-transfer pipe inwall, to passing into 30L/min pure argon (99.95%) in heat-transfer pipe, protected simultaneously, cooling.
Intercepting part sample, records consolidation nitriding depth with microscopic examination and is about 100 μ m, and recording outside surface hardness is HV400.
Intercepting 42mm nitriding pipe is made tension specimen, carries out stress corrosion tension test, and test parameter is with embodiment 1, and test-results is as following table:
1) intercepting 20mm laser melting nitriding pipe carries out fretting wear test
Fretting wear test parameter is with embodiment 1, and test-results is as Fig. 2.
Tensile strength, unit elongation, relative reduction in area, the hardness of laser melting nitriding sample has raising in various degree, crack propagation rate reduces, corrosion resisting property is improved, under normal temperature and pressure, laser melting nitriding sample is more shallow, more wear-resisting than the polishing scratch degree of depth of undressed Inconel690 compo pipe as seen from Figure 2.
Claims (1)
1. a laser processing method that improves nuclear power 690 alloy stress corrosion resistance and wear resistance, when it is characterized in that adopting wavelength to be 800-1070nm continuous laser thermal source remelting 690 alloy heat-transfer pipe outer round surface, auxiliary nitrogen carries out nitriding processing, laser power 300-1000W, laser scanning linear velocity is 200-800mm/min, spot diameter 0.5-3mm, overlapping rate 20-60%, in the time of laser melting 690 compo pipe outer round surface, auxiliary nitrogen carries out nitriding processing, nitrogen flow is 20-30L/min, nitrogen nozzle is 5-12mm to the distance of tube surface, jet exit nitrogen pressure is 0.5-1MPa, the argon gas that 690 heat-transfer pipe endoporus auxiliary flow are 20-30L/min is protected bore surface and cooling tube wall.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104962907A (en) * | 2015-06-29 | 2015-10-07 | 北京工业大学 | Laser alloying processing method for improving surface property of nuclear power 690 alloy pipe |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104962907A (en) * | 2015-06-29 | 2015-10-07 | 北京工业大学 | Laser alloying processing method for improving surface property of nuclear power 690 alloy pipe |
| CN104962907B (en) * | 2015-06-29 | 2017-07-21 | 北京工业大学 | A kind of laser alloying treatment method for improving the compo pipe surface property of nuclear power 690 |
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