CN103480975A - Manufacturing method of nuclear-grade austenitic stainless steel welding wire - Google Patents

Manufacturing method of nuclear-grade austenitic stainless steel welding wire Download PDF

Info

Publication number
CN103480975A
CN103480975A CN201310178968.9A CN201310178968A CN103480975A CN 103480975 A CN103480975 A CN 103480975A CN 201310178968 A CN201310178968 A CN 201310178968A CN 103480975 A CN103480975 A CN 103480975A
Authority
CN
China
Prior art keywords
percent
stainless steel
austenitic stainless
less
equal
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.)
Pending
Application number
CN201310178968.9A
Other languages
Chinese (zh)
Inventor
淮凯文
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
DANYANG HUALONG SUPERIOR STEEL Co Ltd
Original Assignee
DANYANG HUALONG SUPERIOR STEEL Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by DANYANG HUALONG SUPERIOR STEEL Co Ltd filed Critical DANYANG HUALONG SUPERIOR STEEL Co Ltd
Priority to CN201310178968.9A priority Critical patent/CN103480975A/en
Publication of CN103480975A publication Critical patent/CN103480975A/en
Pending legal-status Critical Current

Links

Classifications

    • BPERFORMING OPERATIONS; TRANSPORTING
    • B23MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23KSOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K35/00Rods, electrodes, materials, or media, for use in soldering, welding, or cutting
    • B23K35/22Rods, electrodes, materials, or media, for use in soldering, welding, or cutting characterised by the composition or nature of the material
    • B23K35/24Selection of soldering or welding materials proper
    • B23K35/30Selection of soldering or welding materials proper with the principal constituent melting at less than 1550 degrees C
    • B23K35/3053Fe as the principal constituent
    • B23K35/308Fe as the principal constituent with Cr as next major constituent

Landscapes

  • Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Heat Treatment Of Steel (AREA)

Abstract

The invention discloses a nuclear-grade austenitic stainless steel welding material. The material deposited metal has high low-temperature strength, low-temperature toughness, low-temperature non-magnetism and good neutron irradiation resistance performance, and comprises the following chemical constituents in percentage by weight: 18.00-20.0 percent of Cr, 12.00-14.00 percent of Ni, 2.00-3.00 percent of Mo, 0.06-0.15 percent of N, less than or equal to 0.03 percent of C, 1.00-2.50 percent of Mn, less than or equal to 1.00 percent of Si, 0.01-0.10 percent of Nb, 0.01-0.10 percent of Ta, less than or equal to 0.10 percent of Co, less than or equal to 0.03 percent of P, less than or equal to 0.005 percent of S, less than or equal to 0.0018 percent of B and the balance of iron and impurities generally existing in steelmaking, wherein the Val(Cr-Ni) value is less than 16. The material can be used for welding nuclear-grade materials for manufacturing forgings, plates, tubes and the like.

Description

A kind of core level austenitic stainless steel welding wire manufacture method
 
Technical field
The present invention relates to core level austenitic stainless steel wlding, specially refer to so a kind of austenitic stainless steel alloy composition, have high low temperature intensity, low-temperature flexibility, anti-neutron irradiation performance that low temperature is nonmagnetic and good concurrently.
Stainless steel alloy, corrosion resistance nickel-chromium series austenitic stainless steel alloy particularly, because it has the stability of good corrosion resistance, mechanical property and austenite structure, therefore be widely used in the preparation of fission-type reactor parts, as in-pile component, boron are annotated case, the weary material storage and transportation apparatus of core and nuclear fuel pond.Because the environment for use of this type of application is all high temperature and high pressure environment, so austenitic stainless steel generally all requires to have good room-temperature mechanical property and 350 ℃ of mechanical properties, requires in addition good anti-neutron irradiation performance.
Background technology
The nuclear reactor adopted at present mainly reacts to obtain energy by nuclear fission, when obtaining the energy, also there are the potential dangers such as nuclear leakage, also very limited for the uranium resource storage capacity of fission reaction in addition, can restrict to a certain extent the construction in enormous quantities of such nuclear-power reactor.Along with the progress of mankind's technology, carry out the fission reaction acquisition energy by refinement deuterium and tritium in seawater and progressively enter research field, also start in the world to carry out the exploratory research of nuclear fission and building industry heap type.Magnet support structure in fission-type reactor heap type belongs to a critical component, and these parts are applied under the 77k cryogenic conditions, and the limiting temperature of material is required as 4k.Owing to being support member, need pressure-bearing, also require material to there is good low temperature intensity, want in addition good anti-neutron irradiation performance and nonmagnetic energy.Meeting of its anti-neutron irradiation performance mainly guarantees by Composition Control, guarantee the stress corrosion under its good anti-neutron irradiation environment by controlling the niobium tantalum content, by controlling stability that the large element cobalt in neutron absorption cross-section and boron guarantees this material structure and the failure resistance of material.It is nonmagnetic, and not only to require material to have under the 77k static conditions nonmagnetic, also requires still to have nonmagnetic energy after the certain deflection of carrying at this temperature.That can use at present this generic request only has the steel grades such as 316LN, and this steel grade is also the steel grade of each large steel mill Devoting Major Efforts To Developing these years.
For the welding material of such steel grade, the postwelding commissure should meet the mechanical property of mother metal, also will meet the requirement of environment for use, requires commissure to have high low temperature intensity, low-temperature flexibility, anti-neutron irradiation performance that low temperature is nonmagnetic and good concurrently.At present existing multinomial patent relates to the low temperature austenitic stainless steel, be mainly concerned with low temperature austenitic stainless steel peculiar to vessel, alloying component as disclosed as patent US4675156 is: carbon≤0.05%, 0.20%<nitrogen<0.70%, silicon<1.00%, manganese≤25%, 13%<chromium<35%, 5%<nickel<25%, Yu Weitie, and (Cr+0.9Mn) >=20%, control field trash by controlling aluminium content; The disclosed composition of the clear 60-9862 of open patent is: carbon≤0.05%, 0.20%<nitrogen<0.50%, silicon<1.00%, manganese≤4.0%, 20%<chromium<35%, 8%<nickel<25%, Yu Weitie; These two patents are all that the solid solubility by providing chromium, manganese content to increase nitrogen obtains high low temperature yield strength and low-temperature impact toughness preferably, but also improved its production difficulty when gaining in strength, as restive as field trash in smelting process, thermoplasticity is poor, owing to not containing molybdenum, its pitting resistance is also poor simultaneously.But the research for welding material is not reported for work.
From contrast, can find out patent analyses, the contrast patent is all to put forward heavy alloyed low temperature intensity by improving manganese, chromium, nitrogen and interpolation niobium, but high-intensityly magnetic property and the anti-neutron irradiation performance of material is not controlled carrying simultaneously.This patent is by controlling and the optimization composition, on the one hand when guaranteeing its low-temperature flexibility of wlding, improve its low temperature intensity by niobium, tantalum and nitrogen complex intensifying, on the other hand, elemental niobium, tantalum, cobalt and the boron content of control effect material neutron irradiation performance, guarantee the nonmagnetic energy of its low temperature by controlling the ferrite content in the wlding austenite and increasing austenitic structure stability in addition.
 
Summary of the invention
The object of the present invention is to provide a kind of core and austenitic stainless steel wlding, specially refer to so a kind of austenitic stainless steel alloy composition, have high low temperature intensity, low-temperature flexibility, anti-neutron irradiation performance that low temperature is nonmagnetic and good concurrently.
For above-mentioned purpose, technical scheme of the present invention is when guaranteeing its low-temperature flexibility, improve its low temperature intensity by niobium tantalum and nitrogen complex intensifying, elemental niobium, tantalum, cobalt and the boron of the anti-neutron irradiation performance by the control effect material guarantee the anti-neutron irradiation performance that it is good, guarantee the nonmagnetic energy of its low temperature by the high temperature ferrite content of controlling in austenite with the stability that increases the austenite element, according to above-mentioned principle, thereby a kind of chemical composition (percentage by weight) of core level austenitic stainless steel wlding has been proposed, as follows:
Chromium 18.00~20.00
Nickel 12.00~14.00
Molybdenum 2.00~3.00
Nitrogen 0.06~0.15
Carbon≤0.03
Manganese 1.00~2.50
Silicon≤1.00
Niobium 0.01~0.10
Tantalum 0.01~0.10
Cobalt≤0.10
Phosphorus≤0.03
Sulphur≤0.005
Boron≤0.0018
And make Val (Cr-Ni)value is less than 16, wherein Val (Cr-Ni)the employing following formula calculates:
Val (Cr-Ni)=3*(Cr+Mo)+4.5*Si-2.8*Ni-1.4*Mn-84*(C+N);
Surplus is iron and the impurity existed of usually making steel;
Determine the reasons are as follows of above-mentioned chemical composition:
Carbon: carbon can increase the low temperature intensity of alloy by solution strengthening, but carbon content is too high, and carbide can be separated out and cause grain boundary corrosion performance and cryogenic property to reduce at austenite grain boundary, therefore the carbon content maximum is preferably to 0.03%;
Nickel: nickel is strong austenite former, increase the stability that nickel content contributes to improve austenite structure, but nickel too high levels, can reduce the solid solubility of carbon, cause the corrosion among crystalline grains of steel to reduce, high nickel content is unfavorable for the raising of material at low temperature intensity in addition, therefore is preferably 12~13%.
Chromium: chromium is ferrite former, can obviously increase the decay resistance of alloy, improves the nitrogen solubility in austenitic stainless steel, obtains high low temperature intensity.But the chromium too high levels, can cause in austenite ferrite content to increase, and causes material to have magnetic, and can increase and harmfully separate out mutually, therefore be preferably 18.00~20.00%;
Molybdenum: molybdenum is ferrite former, add the pitting resistance that molybdenum can improve austenitic stainless steel in austenitic stainless steel, can improve its low temperature intensity by solution strengthening, add in addition in 18-8 series austenitic stainless steel, can stablize its austenite structure, avoid producing strain-induced martensite, therefore be preferably 2.00~3.00%.
Manganese: increase the solid solubility that manganese content can improve nitrogen element in austenitic stainless steel, but manganese too high levels, can cause austenitic stainless steel to be out of shape at low temperatures generation martensite, manganese content over 5% even can cause material to be cooled to-196 ℃ of processes produce the martensite phase transformation from room temperature, therefore manganese content is preferably to 1~2.50%;
Nitrogen: nitrogen, as strong austenite former, can obviously improve the low temperature intensity of austenitic stainless steel, also can obviously not reduce its toughness carrying the high-intensity while; Nitrogen and niobium, tantalum interact in addition, can more obviously improve the strength of materials; But nitrogen content is too high, can cause a large amount of nitride to be separated out, can reduce again low-temperature flexibility and the decay resistance of material, therefore be preferably 0.06~0.15%;
Niobium, tantalum: two kinds of elements all can obviously improve the low temperature intensity in austenitic stainless steel by solution strengthening, by with carbon, being combined and can avoiding its intercrystalline corrosion, but too high levels can cause caused anticorrosion stress-resistant hydraulic performance decline and low-temperature impact toughness decline under radiation parameter, therefore both is preferably 0.01~0.10%;
Cobalt: cobalt, because its neutron absorption cross-section is large, easily causes the inefficacy of material under the neutron irradiation condition, therefore controls it as and is less than 0.10%;
Boron: add the grain-boundary strength that appropriate boron can improve austenitic stainless steel, be conducive to improve low temperature intensity and the toughness of material, but boron is the large element in neutron absorption cross-section, add and too much can cause the inefficacy of material under the neutron irradiation condition, therefore control it as and be less than 0.0018%;
Silicon: the deoxidier in steelmaking process, its content is inevitable;
Sulphur, phosphorus: the impurity element in the alloy smelting process, but too much phosphorus content can cause the reduction of its low-temperature flexibility, so control as being less than 0.03%; Sulphur can increase the hot crackability of austenitic stainless steel, and the austenitic stainless steel of especially low ferrite content, therefore control it as and be less than 0.005%;
Rationally determine the content of nickel equivalent forming element Ni, Mn, N, C and chromium equivalent forming element Cr, Si, Mo, make Val (Cr-Ni)value is less than 16, to guarantee nonmagnetic under its cryogenic conditions, Val (Cr-Ni)be worth littlely, show that this austenitic stainless steel nickel equivalent is higher, austenite structure is more stable in the process of deformation.Work as Val (Cr-Ni)be worth when larger, will there be the more amount ferrite content in such austenitic stainless steel, and material does not possess nonmagnetic and structure stability at low temperatures, and the unstability of austenite stainless structure of steel can cause strain-induced martensite occurring after material deformation, also can produce magnetic.
Concrete, the present invention improves the low temperature intensity of austenitic stainless steel according to niobium tantalum and nitrogen complex intensifying, carrying the high-intensity while, taken into account its low-temperature flexibility, guarantee by controlling niobium, tantalum, boron and cobalt content the anti-neutron irradiation performance that it is good simultaneously, by rationally determining the content of nickel equivalent forming element Ni, Mn, N, C and chromium equivalent forming element Cr, Si, Mo, the high temperature ferrite content of controlling in austenitic stainless steel guarantees still have nonmagnetic energy after distortion under its low temperature and low temperature.
Proposed for the above reasons core level austenitic stainless steel wlding of the present invention, the present invention, except having excellent low temperature intensity and toughness, also has good anti-neutron irradiation performance and nonmagnetic energy, can be applicable to the welding of the products such as forging, plate, band.
The present invention adopts the conventional stainless steel mode of production, be that intermediate frequency furnace+vacuum drying oven mode is smelted, forge in 950-1250 ℃ of temperature range and rolling, in 1050-1110 ℃ of scope, carry out solution heat treatment, after pickling, cold rolling or drawing, bright annealing, obtain corresponding product.
The specific embodiment
Illustrate:
The magnetic property of austenitic stainless steel is mainly weighed by measuring its magnetic conductivity, when magnetic conductivity, just means that this material has nonmagnetic energy lower than 1.01 the time; And just mean that this material has certain magnetic when magnetic conductivity during higher than this value, do not reach nonmagnetic can requirement.Under 77K, after material deformation, still having nonmagnetic can be to weigh by carrying out at low temperatures after 2% denaturation measuring its magnetic property again.77K and 4K performance are to take out by material being soaked at this temperature after 4 hours, then at room temperature measure immediately.
embodiment 1
According to austenite stainless composition of steel of the present invention, list in table 2, adopt intermediate frequency furnace+vacuum induction melting, the company's of being cast into slab ingot, be rolled into 5mm after stripping off the skin, at 1080 ℃ of temperature after annealing and pickling, be cold-rolled to then bright annealing of 1.5mm, this sheet material has higher low temperature intensity, toughness, and nonmagnetic energy has guaranteed by controlling niobium, tantalum, cobalt and boron element the anti-neutron irradiation performance that it is good.All properties is listed in table 3.
embodiment 2
According to austenite stainless composition of steel of the present invention, list in table 2, adopt intermediate frequency furnace+vacuum induction melting, be cast into billet, forging is rolled into the 5mm wire rod, after pickling, after multi pass drawing, at 1080 ℃ of bright annealings, becomes 1mm silk material, and this sheet material has higher low temperature intensity, toughness, nonmagnetic energy, guaranteed by controlling niobium, tantalum, cobalt and boron element the anti-neutron irradiation performance that it is good.All properties is listed in table 3.
embodiment 3
According to austenite stainless composition of steel of the present invention, list in table 2, adopt intermediate frequency furnace+vacuum induction melting, the company's of being cast into slab ingot, be rolled into 6mm after stripping off the skin, at 1080 ℃ of temperature after annealing and pickling, be cold-rolled to then bright annealing of 2.0mm, this sheet material has higher low temperature intensity, toughness, and nonmagnetic energy has guaranteed by controlling niobium, tantalum, cobalt and boron element the anti-neutron irradiation performance that it is good.All properties is listed in table 3.
embodiment 4
According to austenite stainless composition of steel of the present invention, list in table 2, adopt intermediate frequency furnace+vacuum induction melting, be cast into billet, forging is rolled into the 5mm wire rod, after pickling, after multi pass drawing, at 1080 ℃ of bright annealings, becomes 1.3mm silk material, and this slab has higher low temperature intensity, toughness, nonmagnetic energy, guaranteed by controlling niobium, tantalum, cobalt and boron element the anti-neutron irradiation performance that it is good.All properties is listed in table 3.
Comparative Examples:
Comparative Examples 1 is conventional 308L wlding, from the performance list, can find out, the performance of Comparative Examples can not guarantee that it is for making the nuclear fusion magnet support.
 
Composition contrast between table 1, different patent, surplus is iron (wt.%)
Figure 2013101789689100002DEST_PATH_IMAGE001
Table 2, embodiment and Comparative Examples composition, surplus is iron (wt.%)
Figure 2013101789689100002DEST_PATH_IMAGE003
Table 3, embodiment postwelding deposited metal and Comparative Examples performance comparison
Figure 2013101789689100002DEST_PATH_IMAGE005

Claims (4)

1. a core level austenitic stainless steel wlding, this material deposited metal has high low temperature intensity, low-temperature flexibility, the anti-neutron irradiation performance that low temperature is nonmagnetic and good, its chemical composition is: Cr:18.00~20.0, Ni:12.00~14.00, Mo:2.00~3.00, N:0.06~0.15, C :≤0.03, Mn:1.00~2.50, Si :≤1.00, Nb:0.01~0.10, Ta:0.01~0.10, Co :≤0.10, P :≤0.03, S :≤0.005, B≤0.0018, and make Val (Cr-Ni) value be less than 16, surplus is iron and the impurity existed of usually making steel.
2. core level austenitic stainless steel wlding as claimed in claim 1, is characterized in that comprising 0.06~0.15% nitrogen.
3. core level austenitic stainless steel wlding as claimed in claim 1, is characterized in that containing 0.01 ~ 0.10% Nb and 0.01 ~ 0.10%Ta.
4. core level austenitic stainless steel wlding as claimed in claim 1, is characterized in that Val (Cr-Ni) value is less than 16.
CN201310178968.9A 2013-05-15 2013-05-15 Manufacturing method of nuclear-grade austenitic stainless steel welding wire Pending CN103480975A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201310178968.9A CN103480975A (en) 2013-05-15 2013-05-15 Manufacturing method of nuclear-grade austenitic stainless steel welding wire

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201310178968.9A CN103480975A (en) 2013-05-15 2013-05-15 Manufacturing method of nuclear-grade austenitic stainless steel welding wire

Publications (1)

Publication Number Publication Date
CN103480975A true CN103480975A (en) 2014-01-01

Family

ID=49821754

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201310178968.9A Pending CN103480975A (en) 2013-05-15 2013-05-15 Manufacturing method of nuclear-grade austenitic stainless steel welding wire

Country Status (1)

Country Link
CN (1) CN103480975A (en)

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104175017A (en) * 2014-08-20 2014-12-03 四川大西洋焊接材料股份有限公司 Stainless-steel gas shielded welding wire for third-generation nuclear main pipelines
CN104195458A (en) * 2014-08-05 2014-12-10 东北大学 Stainless steel hot rolled plate with low relative permeability and preparation method thereof
CN105234590A (en) * 2015-11-18 2016-01-13 四川大西洋焊接材料股份有限公司 SA-508Gr.3Cl.2 steel submerged arc welding agent for nuclear power engineering and special welding wire
CN106563892A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 Corrosion-resisting austenitic stainless steel submerged-arc welding wire and production method thereof
CN106566952A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 High temperature resistance forge piece with excellent nuclear power performance and production method thereof
CN106563888A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 High-cost-performance submerged-arc welding wire and producing method thereof
CN107553004A (en) * 2017-09-28 2018-01-09 中国科学院金属研究所 A kind of sodium-cooled fast reactor austenitic stainless steel bare wire and its application
CN110270775A (en) * 2019-04-23 2019-09-24 安徽科技学院 A kind of anti-neutron irradiation steel metal powder type flux-cored wire
CN112475532A (en) * 2020-10-10 2021-03-12 东方电气集团东方锅炉股份有限公司 Welding process for austenitic stainless steel 316L material in high-pressure hydrogen environment
CN112522472A (en) * 2020-12-24 2021-03-19 广东石油化工学院 Method for smelting and denitrifying stainless steel welding material
CN112553403A (en) * 2020-12-24 2021-03-26 广东石油化工学院 Method for smelting and deoxidizing stainless steel welding material
CN112626313A (en) * 2020-12-24 2021-04-09 广东石油化工学院 Method for smelting and desulfurizing stainless steel welding material

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58141891A (en) * 1982-02-19 1983-08-23 Kawasaki Steel Corp Austenitic steel for build up welding electrode
JPH0788684A (en) * 1993-09-17 1995-04-04 Nippon Steel Corp Welding material for austenitic stainless steel and welding method
CN101484270A (en) * 2006-07-05 2009-07-15 新日本制铁株式会社 Stainless steel wire with flux core for welding zinc coated steel sheets
CN102041457A (en) * 2009-10-20 2011-05-04 宝山钢铁股份有限公司 Austenitic stainless steel
CN102264505A (en) * 2008-12-26 2011-11-30 新日本制铁株式会社 Stainless steel flux-cored welding wire for the welding of galvanized steel sheets and process for arc welding of galvanized steel sheets with the same
CN102649202A (en) * 2011-02-23 2012-08-29 宝山钢铁股份有限公司 Stainless steel welding wire

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58141891A (en) * 1982-02-19 1983-08-23 Kawasaki Steel Corp Austenitic steel for build up welding electrode
JPH0788684A (en) * 1993-09-17 1995-04-04 Nippon Steel Corp Welding material for austenitic stainless steel and welding method
CN101484270A (en) * 2006-07-05 2009-07-15 新日本制铁株式会社 Stainless steel wire with flux core for welding zinc coated steel sheets
CN102264505A (en) * 2008-12-26 2011-11-30 新日本制铁株式会社 Stainless steel flux-cored welding wire for the welding of galvanized steel sheets and process for arc welding of galvanized steel sheets with the same
CN102041457A (en) * 2009-10-20 2011-05-04 宝山钢铁股份有限公司 Austenitic stainless steel
CN102649202A (en) * 2011-02-23 2012-08-29 宝山钢铁股份有限公司 Stainless steel welding wire

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104195458A (en) * 2014-08-05 2014-12-10 东北大学 Stainless steel hot rolled plate with low relative permeability and preparation method thereof
CN104175017A (en) * 2014-08-20 2014-12-03 四川大西洋焊接材料股份有限公司 Stainless-steel gas shielded welding wire for third-generation nuclear main pipelines
CN106563892A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 Corrosion-resisting austenitic stainless steel submerged-arc welding wire and production method thereof
CN106566952A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 High temperature resistance forge piece with excellent nuclear power performance and production method thereof
CN106563888A (en) * 2015-10-10 2017-04-19 丹阳市华龙特钢有限公司 High-cost-performance submerged-arc welding wire and producing method thereof
CN105234590A (en) * 2015-11-18 2016-01-13 四川大西洋焊接材料股份有限公司 SA-508Gr.3Cl.2 steel submerged arc welding agent for nuclear power engineering and special welding wire
CN107553004A (en) * 2017-09-28 2018-01-09 中国科学院金属研究所 A kind of sodium-cooled fast reactor austenitic stainless steel bare wire and its application
CN110270775A (en) * 2019-04-23 2019-09-24 安徽科技学院 A kind of anti-neutron irradiation steel metal powder type flux-cored wire
CN112475532A (en) * 2020-10-10 2021-03-12 东方电气集团东方锅炉股份有限公司 Welding process for austenitic stainless steel 316L material in high-pressure hydrogen environment
CN112475532B (en) * 2020-10-10 2022-03-25 东方电气集团东方锅炉股份有限公司 Welding process for austenitic stainless steel 316L material in high-pressure hydrogen environment
CN112522472A (en) * 2020-12-24 2021-03-19 广东石油化工学院 Method for smelting and denitrifying stainless steel welding material
CN112553403A (en) * 2020-12-24 2021-03-26 广东石油化工学院 Method for smelting and deoxidizing stainless steel welding material
CN112626313A (en) * 2020-12-24 2021-04-09 广东石油化工学院 Method for smelting and desulfurizing stainless steel welding material

Similar Documents

Publication Publication Date Title
CN103480975A (en) Manufacturing method of nuclear-grade austenitic stainless steel welding wire
CN102041457B (en) Austenitic stainless steel
CN105624550B (en) Nuclear island equipment big thickness SA738GrB steel plates and production method
CN104328353B (en) A kind of rare-earth type 0Cr17Ni4Cu4Nb martensitic precipitations and preparation method thereof
CN109207846A (en) A kind of high anti-corrosion section nickel high-nitrogen austenitic stainless steel
CN103317256A (en) Austenitic stainless steel submerged-arc welding wire with excellent high-temperature strength
CN102899582B (en) High strength nickel base corrosion resistance alloy and manufacturing method thereof
CN103521946A (en) High-strength austenitic stainless steel submerged-arc welding wire
CN109136652B (en) Nickel-based alloy large-section bar for nuclear power key equipment and manufacturing method thereof
CN103276296B (en) Manufacturing method of Martensite stainless steel ring-shaped forging piece
CN113430445A (en) FeCrNiAlMoNb high-entropy alloy and preparation method thereof
CN109136653A (en) For the nickel-base alloy of nuclear power generating equipment and its manufacturing method of hot rolled plate
CN105849302A (en) Steel for low-temperature service having excellent surface processing quality
CN103352175A (en) Nitrogen-containing austenitic stainless steel and manufacturing method thereof
CN102605296A (en) Steel for nuclear pressure vessels and manufacturing method thereof
CN113737091A (en) Steel for low-magnetism high-strength corrosion-resistant fastener and fastener
CN102409258B (en) Structural homogeneity control method of boron-containing high strength hydrogen resistant brittle alloy
CN106381452B (en) The heat-resisting austenitic stainless steel of high structure stability at a kind of 700 DEG C
CN105331905B (en) Novel non-magnetic stainless steel and preparation method thereof
US4385933A (en) Highly heat resistant austenitic iron-nickel-chromium alloys which are resistant to neutron induced swelling and corrosion by liquid sodium
CN112410517B (en) Method for eliminating delta ferrite in austenitic stainless steel
CN111647790B (en) Preparation method and application of high-strength high-toughness iron-nickel-chromium-based heat-resistant alloy
CN106566952A (en) High temperature resistance forge piece with excellent nuclear power performance and production method thereof
CN105839027A (en) Nickel-based corrosion-resistant alloy and manufacturing method thereof
Rao Materials development for indian nuclear power programme: an industry perspective

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C02 Deemed withdrawal of patent application after publication (patent law 2001)
WD01 Invention patent application deemed withdrawn after publication

Application publication date: 20140101