CN104164539B - A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance - Google Patents
A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance Download PDFInfo
- Publication number
- CN104164539B CN104164539B CN201410361414.7A CN201410361414A CN104164539B CN 104164539 B CN104164539 B CN 104164539B CN 201410361414 A CN201410361414 A CN 201410361414A CN 104164539 B CN104164539 B CN 104164539B
- Authority
- CN
- China
- Prior art keywords
- laser
- nitrogen
- heat
- carries out
- alloy
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Landscapes
- Heat Treatment Of Articles (AREA)
- Laser Beam Processing (AREA)
Abstract
The present invention relates to a kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance. while adopting wavelength to be 800-1070nm continuous laser thermal source remelting 690 alloy heat-transfer pipe outer round surface, auxiliary nitrogen carries out Nitrizing Treatment, laser power 300-1000W, laser scanning linear velocity is 200-800mm/min, spot diameter 0.5-3mm, overlapping rate 20-60%, while laser melting 690 compo pipe outer round surface, auxiliary nitrogen carries out Nitrizing Treatment, 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, in 690 heat-transfer pipes, hole auxiliary flow is that the argon gas of 20-30L/min carries out protection bore surface and cooling tube wall. it adopts laser melting to carry out Nitrizing Treatment to the method for the logical nitrogen of molten coagulation zone in 690 alloy tube surface simultaneously, obtains the fine and close nitrided case of 20-100 �� m-thick, thus improves stress corrosion resistance and wear resistance.
Description
Technical field
The present invention relates to a kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance, belong to Materialbearbeitung mit Laserlicht field.
Background technology
Relative to traditional thermoelectricity, water power equal energy source system, the energy resource supply of the mankind, as a kind of safe, cleaning, economic novel energy, is played a part to replace by nuclear power. The area of pressurized water reactor nuclear power station steam generator heat-transfer pipe accounts for about the 80% of primary Ioops pressure-bearing boundary area, heat-transfer pipe wall thickness is generally 1mm��1.2mm, it it is part the weakest in whole primary Ioops pressure boundary, external service experience shows, because steam generator heat-transfer pipe damages, impact normally runs, reduces Power operation or be forced to shutdown the pressurized-water reactor of about 30%��40%. 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, the problem of 60% belongs to stress corrosion problem. Simultaneously during pressurized-water reactor nuclear power plant normal operation, the heat-transfer pipe caused due to Flow vibration and liner plate generation fretting wear, too increase the tendency of heat-transfer pipe corrosion cracking.
Inconel690 alloy is high Cr nickel-base alloy, is mainly used in corrodibility 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 runs also only less than the history of 30 years as the vapour generator of heat transfer tubing, and stress corrosion crack problem and fretting wear problem occurs in the heat-transfer pipe also having had a small amount of this kind of material abroad. Therefore solve vapour generator to break and run affairs therefore be related to the security of Nuclear power plants and make Nuclear power plants have key issue that is competitive and vitality.
In the retrieval to existing patent, find the patent of invention (patent No. 101974773A of " a kind of method improving Inconel690 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 carries out surface modification. But the electrodeposited chromium technique that this patent adopts, its chromium coating easily comes off, and is easily polluted by environment in electroplating process, and electrodeposited chromium too increases transportation cost with being separated of laser processing, is unfavorable for site disposal.
Summary of the invention
The object of the present invention is exactly to solve heat-transfer pipe stress corrosion crack and fretting wear problem, thering is provided a kind of method improving nuclear power 690 alloy heat-transfer pipe stress corrosion resistance and wear resistance, it can make the ability of heat-transfer pipe opposing stress corrosion and wear resisting property be largely increased.
For achieving the above object, the present invention adopts following technical scheme:
A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance, while 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 Nitrizing Treatment, , laser power 300-1000W, laser scanning linear velocity is 200-800mm/min, spot diameter 0.5-3mm, overlapping rate 20-60%, while laser melting 690 compo pipe outer round surface, auxiliary nitrogen carries out Nitrizing Treatment, 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, in 690 heat-transfer pipes, hole auxiliary flow is that the argon gas of 20-30L/min carries out protection bore surface and cooling tube wall.
Obtaining thickness is 20-100 ��m of fine and close nitrided case, and hardness brings up to HV200-400.
This technique comprises step specific as follows:
1.Inconel690 alloy tube surface adopts alcohol to clean in advance, remove surface impurity.
2. being fixed on by heat-transfer pipe on lathe turntable, 690 alloy tube surface are carried out laser melting while rotating by turntable, and carry out Nitrizing Treatment with nozzle to the logical high pure nitrogen of molten coagulation zone.
3. it is equipped with pure argon in heat-transfer pipe while of Nitrizing Treatment to protect, prevents heat affected zone alloy to be oxidized.
Laser melting nitriding (LaserMeltingandNitriding, 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%
Nozzle place nitrogen pressure 0.5-1MPa
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: more elongated pressurized water reactor nuclear power station steam generator heat-transfer pipe can be carried out surface treatment by the inventive method, and the laser nitrided case compact structure obtained, homogeneous microstructure, its stress corrosion resistance and wear resistance significantly improve, and adopt short wavelength laser nitriding, light can be more effective by Matrix absorption, it is to increase nitriding efficiency.
Accompanying drawing explanation
Fig. 1 is laser melting nitriding schematic diagram
1,690 heat-transfer pipe outside surface; 2, lathe turntable; 3, laser system; 4, nitriding nozzle; 5, argon nozzle (engaging with heat-transfer pipe inner wall sealing); 6, nitride layer; 7, heat-transfer pipe inwall; 8, molten coagulation zone; 9, heat affected zone
Wear track depth figure 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, the linear velocity of 690 alloy heat-transfer pipe cylindricals is made to reach 200mm/min, adopt wavelength to be that the optical fiber laser of 1070nm carries out surface treatment simultaneously, 690 alloy tube surface are carried out molten solidifying by laser thermal source 3, laser output power is 300W, spot diameter after focusing is 0.5mm, scanning overlapping rate is 20%, the nitriding nozzle 4 being fixed on laser system periphery sends into the high pure nitrogen (99.995%) of top hole pressure as 0.5MPa to laser irradiation region taking the flow of 20L/min, the distance of nitriding nozzle distance tube surface is 12mm, lead to 20L/min in heat-transfer pipe by the argon nozzle 5 connecting heat-transfer pipe inwall simultaneously and protect into pure argon (99.95%), cooling, heat-transfer pipe is prevented to be oxidized.
Intercepting part sample, the mean thickness recording molten solidifying nitrided case 6 with microscopic examination is about 20 ��m, and recording outside surface hardness is HV200.
Intercepting 42mm nitriding pipe and make tension specimen, carry out stress corrosion tension test, test strain rate is 1 �� 10-6s-1, test(ing) medium 50%NaOH+0.3%SiO2+ 0.3%Na2S2O3(massfraction composition) solution. Test-results is such as following table:
In table: the unit elongation of �� sample
The relative reduction in area of RA sample
CGR SCC crack growth rate
I SCC sensitivity indices (stress-strain curve integral area)
UTS maximum stress
1) intercept 20mm laser melting nitriding pipe and carry out fretting wear test
A. experimental installation: PLINT fretting apparatus;
B. friction pair: 1Cr13 stainless steel solid right cylinder (�� 10mm �� 20mm), surface roughness Ra=0.02 ��m;
C. test parameter: normal load is respectively Fn=20,50,80N, cycle index 20000 times, displacement amplitude 100 ��m, frequency 2Hz, normal temperature and pressure;
D. test-results is such as Fig. 2.
Embodiment 2:
Described laser melting nitriding process is: molten solidifying nitriding pre-treatment is with embodiment 1, the semiconductor laser that employing wavelength is 980nm carries 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 being fixed on laser system periphery sends 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, lead in heat-transfer pipe by the argon nozzle connecting heat-transfer pipe inwall simultaneously and protect into 25L/min pure argon (99.95%), cooling.
Intercepting part sample, record molten solidifying nitrided case mean thickness with microscopic examination and be about 72 ��m, recording outside surface hardness is HV280.
Intercepting 42mm nitriding pipe and make tension specimen, carry out stress corrosion tension test, test parameter is with embodiment 1, and test-results is such as following table:
1) intercept 20mm laser melting nitriding pipe and carry out fretting wear test
Fretting wear test parameter is with embodiment 1, and test-results is such as Fig. 2.
Embodiment 3:
Described laser melting nitriding process is: molten solidifying nitriding pre-treatment is with embodiment 1, the semiconductor laser that employing wavelength is 800nm carries 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 being fixed on laser system periphery sends 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, lead in heat-transfer pipe by the argon nozzle connecting heat-transfer pipe inwall simultaneously and protect into 30L/min pure argon (99.95%), cooling.
Intercepting part sample, record molten solidifying nitriding depth with microscopic examination and be about 100 ��m, recording outside surface hardness is HV400.
Intercepting 42mm nitriding pipe and make tension specimen, carry out stress corrosion tension test, test parameter is with embodiment 1, and test-results is such as following table:
1) intercept 20mm laser melting nitriding pipe and carry out fretting wear test
Fretting wear test parameter is with embodiment 1, and test-results is such as Fig. 2.
The tensile strength of laser melting nitriding sample, unit elongation, relative reduction in area, hardness have and improve in various degree, crack propagation rate reduces, corrosion resisting property is improved, as seen from Figure 2 under normal temperature and pressure, laser melting nitriding sample is more shallow, more wear-resisting than the Wear track depth of undressed Inconel690 compo pipe.
Claims (1)
1. one kind is improved the laser processing method of nuclear power 690 alloy stress corrosion resistance and wear resistance, while 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 Nitrizing Treatment, laser power 300-1000W, laser scanning linear velocity is 200-800mm/min, spot diameter 0.5-3mm, overlapping rate 20-60%, while laser melting 690 compo pipe outer round surface, auxiliary nitrogen carries out Nitrizing Treatment, 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, in 690 heat-transfer pipes, hole auxiliary flow is that the argon gas of 20-30L/min carries out protection bore surface and cooling tube wall.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410361414.7A CN104164539B (en) | 2014-07-27 | 2014-07-27 | A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410361414.7A CN104164539B (en) | 2014-07-27 | 2014-07-27 | A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104164539A CN104164539A (en) | 2014-11-26 |
| CN104164539B true CN104164539B (en) | 2016-06-01 |
Family
ID=51908520
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410361414.7A Active CN104164539B (en) | 2014-07-27 | 2014-07-27 | A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104164539B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH024990A (en) * | 1988-06-24 | 1990-01-09 | Hino Motors Ltd | Method for hardening surface of steel |
| JPH07305111A (en) * | 1994-03-18 | 1995-11-21 | Kobe Steel Ltd | High workability steel sheet and method for increasing its strength by irradiation of high density energy |
| US6143095A (en) * | 1997-07-29 | 2000-11-07 | Korea Atomic Energy Research Institute | Method for surface-alloying on metal or alloy substrates, or for surface-repairing the damaged (or failed) metal or alloy substrates using a laser beam |
| CN102560505A (en) * | 2010-12-17 | 2012-07-11 | 中国石油大学(华东) | Composite abrasion-resisting corrosion-resisting self-lubricating film and preparation method thereof |
| CN102978628A (en) * | 2012-11-27 | 2013-03-20 | 中国人民解放军空军工程大学 | Method for carrying out anatonosis by adopting laser plasma impact wave in chemical heat treatment process |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100190506B1 (en) * | 1996-08-23 | 1999-06-01 | 이종훈 | Repairing method of stress corrosion cracking |
-
2014
- 2014-07-27 CN CN201410361414.7A patent/CN104164539B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH024990A (en) * | 1988-06-24 | 1990-01-09 | Hino Motors Ltd | Method for hardening surface of steel |
| JPH07305111A (en) * | 1994-03-18 | 1995-11-21 | Kobe Steel Ltd | High workability steel sheet and method for increasing its strength by irradiation of high density energy |
| US6143095A (en) * | 1997-07-29 | 2000-11-07 | Korea Atomic Energy Research Institute | Method for surface-alloying on metal or alloy substrates, or for surface-repairing the damaged (or failed) metal or alloy substrates using a laser beam |
| CN102560505A (en) * | 2010-12-17 | 2012-07-11 | 中国石油大学(华东) | Composite abrasion-resisting corrosion-resisting self-lubricating film and preparation method thereof |
| CN102978628A (en) * | 2012-11-27 | 2013-03-20 | 中国人民解放军空军工程大学 | Method for carrying out anatonosis by adopting laser plasma impact wave in chemical heat treatment process |
Non-Patent Citations (6)
| Title |
|---|
| Characteristic features of laser-nitrided surfaces of two titanium alloys;S.Mridha et al.;《Materials Science and Engineering》;19910815;第142卷(第1期);第115-124页 * |
| Inconel690合金管镀铬层激光处理工艺研究;邓化凌等;《热加工工艺》;20120730;第41卷(第1期);第155-160页 * |
| Inconel690合金表面处理方法的研究进展;戴海娜等;《金属热处理》;20111025;第36卷(第10期);第38-41页 * |
| Surface nitridation of titanium by pulsed Nd:YAG laser irradiation;E. György et al.;《Applied Surface Science》;20020128;第186卷(第1-4期);第130-134页 * |
| Surface nitridation of transition metals by pulsed laser irradiation in gaseous nitrogen;J.D.Wu et al.;《Surface and Coatings Technology》;19971125;第96卷(第2-3期);第330-336页 * |
| 镀铬Inconel690合金管YAG激光熔凝层的结构及元素扩散;邓化凌等;《热加工工艺》;20130725;第42卷(第14期);第120-121页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN104164539A (en) | 2014-11-26 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| AU2006227582B2 (en) | First wall components for a fusion reactor | |
| McClintock et al. | Initial observations of cavitation-induced erosion of liquid metal spallation target vessels at the Spallation Neutron Source | |
| KR101690202B1 (en) | Method for surface processing a zirconium of hafnium alloy, and component processed in this manner | |
| CN102510909A (en) | Austenitic stainless steel | |
| CN104164539B (en) | A kind of laser processing method improving nuclear power 690 alloy stress corrosion resistance and wear resistance | |
| CN114297796A (en) | Service life assessment method for dissimilar steel welding joint of power station boiler | |
| KR100964172B1 (en) | Method to prevent corrosion degradation using Ni-metal or Ni-alloy plating | |
| CN105063547B (en) | A kind of atmospheric laser passivation prepares the method and its device of the anticorrosive protective layer of uranium surface | |
| CN103084738A (en) | Underwater laser cutter adaptable to water 50 meters deep | |
| CN101633109B (en) | Method for reproducing high-temperature fatigue damage component | |
| TW201535413A (en) | Apparatuses and methods for structurally replacing cracked welds in nuclear power plants | |
| CA2798554A1 (en) | Double-walled tube with interface gap and production method therefor | |
| Salenko et al. | Methods of cutting for workpieces of hardmetal and cBN-based polycrystalline superhard material | |
| Kim et al. | Oxidation behavior and mechanical property of Cr-coated zirconium cladding prepared by 3D laser coating | |
| Yao et al. | Laser hardening techniques on steam turbine blade and application | |
| CN104962907A (en) | Laser alloying processing method for improving surface property of nuclear power 690 alloy pipe | |
| Nemecek et al. | Laser hardening of gear wheels | |
| CN101537542B (en) | 2.25Cr-1Mo steel butt joint welding structure with low welding residual stress | |
| CN105333238B (en) | Metal ceramic composite oil pipe manufactured by remanufacturing waste oil pipe and remanufacturing process thereof | |
| JP2014037957A (en) | Tube sheet of steam generator having anticorrosive layer and manufacturing method thereof | |
| CN102925853A (en) | Ultrahigh nitrogen austenite phase diffusion hardening covering layer for pump shafts of nuclear grade pumps | |
| CN101671766A (en) | Cross head surface induction hardening method of marine diesel engine | |
| CN114231729A (en) | Laser shock peening method for workpiece | |
| KR860000040B1 (en) | Method for hardening of filger dies | |
| CN109518013A (en) | A kind of method of pulse laser remelting purified metal uranium surface, its device and its purification layer of preparation |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant |