CN107287509A - A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method - Google Patents

A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method Download PDF

Info

Publication number
CN107287509A
CN107287509A CN201610203419.6A CN201610203419A CN107287509A CN 107287509 A CN107287509 A CN 107287509A CN 201610203419 A CN201610203419 A CN 201610203419A CN 107287509 A CN107287509 A CN 107287509A
Authority
CN
China
Prior art keywords
steel
steel plate
nuclear power
stablizer
present
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
CN201610203419.6A
Other languages
Chinese (zh)
Inventor
王勇
李德刚
王爽
孙殿东
王永才
颜秉宇
胡海洋
罗志华
李黎明
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.)
Angang Steel Co Ltd
Original Assignee
Angang 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 Angang Steel Co Ltd filed Critical Angang Steel Co Ltd
Priority to CN201610203419.6A priority Critical patent/CN107287509A/en
Publication of CN107287509A publication Critical patent/CN107287509A/en
Pending legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C38/00Ferrous alloys, e.g. steel alloys
    • C22C38/04Ferrous alloys, e.g. steel alloys containing manganese
    • CCHEMISTRY; METALLURGY
    • C21METALLURGY OF IRON
    • C21DMODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D6/00Heat treatment of ferrous alloys
    • C21D6/005Heat treatment of ferrous alloys containing Mn
    • CCHEMISTRY; METALLURGY
    • C21METALLURGY OF IRON
    • C21DMODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D8/00Modifying the physical properties by deformation combined with, or followed by, heat treatment
    • C21D8/02Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips
    • C21D8/0221Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the working steps
    • C21D8/0226Hot rolling
    • CCHEMISTRY; METALLURGY
    • C21METALLURGY OF IRON
    • C21DMODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
    • C21D8/00Modifying the physical properties by deformation combined with, or followed by, heat treatment
    • C21D8/02Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips
    • C21D8/0247Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the heat treatment
    • C21D8/0263Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the heat treatment following hot rolling
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C38/00Ferrous alloys, e.g. steel alloys
    • C22C38/02Ferrous alloys, e.g. steel alloys containing silicon
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C38/00Ferrous alloys, e.g. steel alloys
    • C22C38/08Ferrous alloys, e.g. steel alloys containing nickel
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C38/00Ferrous alloys, e.g. steel alloys
    • C22C38/12Ferrous alloys, e.g. steel alloys containing tungsten, tantalum, molybdenum, vanadium, or niobium
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C38/00Ferrous alloys, e.g. steel alloys
    • C22C38/18Ferrous alloys, e.g. steel alloys containing chromium

Abstract

The present invention provides a kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method, and the composition of the steel plate is as follows by weight percentage:C:0.10%~0.20%, Si:0.10%~0.40%, Mn:1.30%~1.60%, Mo:0.40~0.60%, Ni:0.60%~0.80%, Cr:0.25%~0.45%, V:0.02%~0.05%, surplus is Fe and inevitable impurity.Manufacture method includes smelting, forges, rolls, being heat-treated, and after invention steel plate is conditioned, preferable strength level is respectively provided with different conditions:After steel plate of the present invention is conditioned, 20 DEG C of impact absorbing energy under different conditions are equally maintained at higher level, not only meet the requirement of index, and with larger surplus.

Description

A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method
Technical field
The invention belongs to ferrous material field, more particularly to more particularly to 550MPa grades of core Electric voltage-stablizer equipment steel and its manufacture method.
Background technology
Nuclear energy is as a kind of cleaning, the safe and stable energy, increasingly by countries in the world Attention, safe utilization nuclear energy, greatly develop nuclear power turn into a kind of trend.China is current Through as building the most country of nuclear power generating sets in the world, while as nuclear power technology exporting country, Priority and the national signing related protocol such as South Africa, Pakistan, Turkey, are that it is built first Enter nuclear power generating sets.Wherein in Nuclear island equipment voltage-stablizer belong to core one-level equipment, due to need with Aqueous phase contact with radioactive high temperature, high pressure, therefore application site is extremely crucial.Simultaneously To ensure safety, reducing weld seam, it is generally the case that voltage-stablizer cylinder is by upper, middle and lower three Block steel plate is suppressed, is welded, and every piece of steel plate thickness is 119mm.End socket of voltage regulator by it is upper, Low head is constituted, and each end socket is formed by a steel plate compacting, and steel plate thickness is 100mm, Therefore above-mentioned steel plate not only super thick, but also ultra-wide (width is more than 4000mm), simultaneously It is more strict in terms of combination property requirement, therefore from domestic and international existing iron and steel enterprise's equipment capability From the point of view of, producing such steel plate has larger difficulty.
The enterprise for producing such steel plate in the world at present is mainly French Industeel, and steel grade is 16MND5 as defined in RCC-M M2126 standards, the mode of production is using large-scale steel ingot rolling Form.The problem of being primarily present from the point of view of its condition of production in terms of two:One is by RCC-M M2126 standards are produced, and the control of the constituent content such as C and Ni, Mo in steel is closed not to the utmost Reason, modifier treatment (hereinafter referred to as QT) although tempered sorbite tissue can be obtained afterwards, Again through long-time Simulated post-weld heat treatment (hereinafter referred to as SPWHT), a large amount of conjunctions can be separated out in steel Golden carbide, so as to cause intensity and toughness to decline, it is difficult to meet and require.Under normal circumstances, Such steel can only meet the SPWHT of 10 small left and right, and be difficult to meet in actual production and be up to The SPWHT requirements of 16-16.5 hours;Two be the usual feelings into steel plate by steel ingot Direct Rolling Due to the limitation of mill capacity under condition, steel plate centre can not fully participate in deformation, therefore one A little center porosities, crackle can not obtain effective soldering, so as to cause flaw detection not conform to, this is for core It is extremely fatal for first device steel.
The present invention is improved by practice in terms of alloying element, introducing solution strengthening, Precipitation strength and refined crystalline strengthening mechanism, then coordinate suitable rolling and Technology for Heating Processing, so as to protect Demonstrate,prove performance of the steel plate under different conditions and meet requirement;Hydraulic press advantage is utilized simultaneously, by steel ingot It is forged into suitable steel billet, it is ensured that the defect soldering of steel billet centre, dense structure, from basic On solve above mentioned problem.
More patent and document have been formed to midium-carbon steel both at home and abroad at present《Nuclear power plant containment shell With steel plate and its manufacture method》(application number:201210269122.1), disclose a seed nucleus Power plant safety shell steel plate, its thickness is 10-60mm, and its chemical composition is:C: 0.06-0.15%;Si:0.10-0.40%;Mn:1.0-1.5%;Mo:0.10-0.30%;P≤ 0.012%;S≤0.003%;Al:0.015-0.050;Ni:0.20-0.50%;And V≤0.05%, Ti≤0.03%, Cr≤0.25, Nb≤0.03%, Ca:At least one of 0.0005-0.005%; Surplus is Fe and other inevitable impurity.The nuclear power plant containment shell related generally to thickness steel Plate has high intensity, a high tenacity, and at low temperatures mother metal and heat affected area all have it is good Good impact flexibility, is suitably applied nuclear power plant containment shell manufacture field.
《A kind of generation Ⅲ nuclear power station containment vessel steel plate and its manufacture method》(application Number:201210282831.3), relate generally to a kind of generation Ⅲ nuclear power station containment vessel use Steel plate and its manufacture method, its composition range is:C:0.08-0.12%;Si:0.15-0.55%; Mn:0.9-1.5%;P≤0.007%;S≤0.004%;Ni:0.1-0.5%;Cr:0.0-0.3%; Mo:0.10-0.35%;V:0.010-0.050%;Nb:0.010-0.030%;Ti:0.008-0.035%; Al:0.020-0.050%;N≤0.006%;Nb+V≤0.08%, surplus is iron and inevitable Impurity.Steel plate produced by the present invention, tensile strength reaches more than 600MPa, resistance to 200 DEG C High-temperature behavior, with low cost, welding performance is excellent.But examine nuclear reactor safety shell steel plate An important technology index be steel plate after Simulated post-weld heat treatment mechanical property, in the patent The performance of its Simulated post-weld heat treatment is not referred to.
Invent for above-mentioned two and all refer to the construction of nuclear reactor safety shell, and the invention mainly relates to Core level equipment safety injection tank housing build.
《A kind of Clad steel plate for nuclear power engineering and manufacturing method of clad steel plate and preparation method thereof》(application number: 201210349026.8), relate generally to a kind of Clad steel plate for nuclear power engineering and manufacturing method of clad steel plate, comprising substrate and Compound plate, substrate is killed steel steel plate, and compound plate is chromiumnickel austenite stainless steel steel plate.Substrate composition For:C≤0.025%;Si:0.10-0.50%;Mn:1.00-1.80%;P≤0.015%;S≤ 0.015%;Ni:0.30-0.80%;Cr≤0.25%;Mo:0.35-0.70%;Cu≤0.12%; V≤0.06%;Nb≤0.02%;Ti≤0.03%;Co≤0.25%;Al >=0.02%, surplus For iron and inevitable impurity.The patent is in addition to steel plate chemical composition is disclosed, and emphasis is disclosed The preparation method of clad steel plate, although refer to the composition of substrate and compound plate, but for compound The rolling mill practice and Technology for Heating Processing of steel plate are not proposed.
《A kind of nuclear plant pressure vessels and equipment gate steel plate and its manufacture method》(application Number:201310076884.4), relate generally to a kind of nuclear plant pressure vessels and equipment gate is used Steel plate, steel plate includes:C:0.10-0.20%;Si:0.15-0.35%;Mn:1.00-1.65%;P ≤ 0.015%;S≤0.005%;Ni:0.50-0.85%;Cr≤0.15%;Cu≤0.06%; Mo≤0.05%;V≤0.020%;Nb≤0.040%;Ti≤0.020%;Al:0.020-0.050%; N≤0.015%;As≤0.015%;Sn≤0.010%, surplus is iron and inevitable impurity. The patent is essentially disclosed uses converter smelting under the conditions of existing equipment, realizes clean steel Production.Plate Production cost is low simultaneously, with stable structure property, low-temperature flexibility and high temperature Performance, welding performance, cold and hot working function admirable, its ductile-brittle transition temperature TNDT≤- 28 ℃.But compared with the present invention, one side purposes is different, and (the invention mainly relates to Nuclear island equipment --- safety injection tank casing substrate steel), contrast patent is organized as ferrite+pearlite, and It is normalizing that condition of heat treatment is proposed in the invention.
《A kind of Steel plate with super-large thickness for nuclear power engineering equipment》 (201210309621.9), relate generally to a kind of Steel plate with super-large thickness for nuclear power engineering equipment and Production method, belongs to technical field of steel production.Chemical composition includes:C≤0.020%; Si:0.10-0.30%;Mn:1.15-1.60%;P≤0.012%;S≤0.010%; Ni:0.50-0.80%;Cr≤0.20%;Mo:0.45-0.55%;Cu≤0.18%;V≤0.01%; Nb≤0.02%;Ti≤0.03%;Al is always >=0.020%;Cu+6Sn≤0.33%, surplus is Iron and inevitable impurity.The patent be mainly used in nuclear power plant evaporator, high pressure cover end and The manufacture of the key equipments such as pressure vessel.Though also belong to special heavy plate with steel plate of the present invention (thickness >=100mm), but exist substantially not in composition design, production technology and aspect of performance Together.
《A kind of nuclear power station mechanical module support member high strength steel plate and its manufacture method》(Shen Please number:201310083274.7), a kind of nuclear power station module support member steel plate is related generally to, Composition includes:C:0.08-0.22%;Si:0.15-0.45%;Mn:0.60-1.10%;P≤0.020%; S≤0.015%;Ni:0.60-1.00%;Cr:0.40-0.70%;Cu:0.15-0.55%; Mo:0.40-0.60%;V:0.020-0.080%;Ti:0.008-0.030%;B:0.0005-0.005%; Al:0.020-0.050%, surplus is iron and impurity.The patent is fitted in low carbon content design basis When addition alloying element, the tensile strength of steel is set to reach more than 800MPa.It is disadvantageous in that, Thickness specification is only limitted to 6-65mm, ballistic work average value for 160Mpa, is unsuitable for safety injection tank The manufacture of substrate.
Document " nuclear pressure container steel plate SA533B tissue and mechanical property,《Material Material heat treatment journal》, volume 2012,33, the 8th phase " and report a kind of 620MPa grades of core Voltage force Vessel Steels, it has the precipitation of molybdenum after Simulated post-weld heat treatment, made in sheet material tissue The toughness reduction of sheet material;Document " nuclear power pressure vessel forging 16MND5 Heat-Treatments of Steel Technique,《Steel research journal》, volume 2012,21, the 1st phase " report using forging The method of technique productions 16MND5 steel, is given birth to the present invention using forging, rolling bonding technique There is production cost height, cycle in production, while the two is in Composition Control, other productions There is larger difference in process aspect;" the advanced heap-type of nuclear power and China's nuclear power developing,《Chinese engineering Science》, volume 2005,7, o. 11th " mainly introduce be nuclear power generating sets heap-type and I The development of state's nuclear power technology, specific equipment and steel grade are not related to, has larger difference with the present invention Not.
From the point of view of above-mentioned patent and document contrast, the 550MPa level nuclear powers mentioned with the present invention There is larger difference in voltage-stablizer equipment steel, cannot be used for manufacture nuclear power end socket of voltage regulator, The equipment such as cylinder.
The content of the invention
What this practicality was invented aims to overcome that above mentioned problem and deficiency and provides a kind of 550MPa Level nuclear power voltage-stablizer equipment steel and its manufacture method, steel plate is in quenched and tempered state (QT), simulation weldering The mechanical property of heat treatment state (SPWHT) two states keeps higher level, steel plate afterwards Intensity and toughness matching at thickness 1/4, at 1/2 are good, tissue stabilization, fully meet core The demand that the equipment such as group of motors end socket of voltage regulator, cylinder are built.
The object of the present invention is achieved like this:
A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel, the composition by weight hundred of the steel plate Divide as follows than counting:C:0.10%~0.20%, Si:0.10%~0.40%, Mn:1.30%~ 1.60%th, Mo:0.40~0.60%, Ni:0.60%~0.80%, Cr:0.25%~0.45%, V:0.02%~0.05%, surplus is Fe and inevitable impurity.Impurity element in steel Control:P≤0.012%, S≤0.008%, [H]≤2.0ppm, [O]≤30ppm.
Composition design reason is as follows:
C:C is the essential element for ensureing armor plate strength in steel, and in the technical program, C contains Amount is less than 0.10%, and tensile strength would generally can not meet requirement, particularly through 16 small durations Intensity can further decline after time SPWHT.It is mainly shown as thick steel plates thickness 1/2 And be difficult to obtain preferable tempered sorbite tissue at 1/4, matrix solution strengthening effect is not enough; On the contrary, C content is more than 0.20%, it can directly cause the decline of toughness plasticity.Therefore the present invention will It is 0.10%~0.20% to seek C content scope in steel, and preferably control range is 0.10%-0.16%.
Si:Si is effective intensified element, plays deoxidation, is required in the technical program Si contents are not less than 0.10%;But content is higher to bring toughness plasticity to decline, and deteriorates weldability Can, therefore control Si upper content limits to be 0.40%.And collateral security steel plate different conditions obdurability From the aspect of energy, the control of Si contents is limited in, i.e., preferred control range is 0.20%-0.30%.
Mn:Mn elements are in addition to playing reinforcing matrix in steel, moreover it is possible to effectively improve steel Quenching degree, similarly help to improve intensity but reduce tough, plasticity, therefore the technical program The control of Mn contents is 1.30%~1.60%.Mn contents are preferably controlled in actual production steel The upper limit, i.e., preferred control range is 1.40%-1.60%.
Mo:Mo effect be improve quenching degree, heat resistance, and with Cr, Mn collective effect Reduce or suppress temper brittleness.When the control of Mo contents is 0.5% or so in steel, Ji Huke So that temper brittleness is completely eliminated;But when Mo contents are less than 0.20% or more than 0.80%, then It is little to the action effect of the Low-Temperature Temper Brittleness of steel, it is thus determined that being in Mo composition ranges 0.40~0.60%, it is 0.45%-0.55% preferably to control Mo contents.
Ni:Ni can be obviously improved the low-temperature flexibility of steel, while improving the low of thick section steel plate Warm toughness, makes steel plate also have higher toughness while with sufficient intensity, meets index Requirement.In view of steel plate thickness >=100mm of the present invention, for ensure intensity and it is tough, Plasticity reaches preferable matching, therefore Ni contents of the present invention are defined as:0.60%~0.80%.
Cr:Cr can significantly improve the antioxidation of steel in steel, increase resistance to corrosion. Austenite phase field is reduced simultaneously, improves the through hardening performance of steel.But Cr can also significantly improve steel Brittle transition temperature, promotes temper brittleness.Intensity during to be further ensured that steel plate different conditions Stability, Cr contents control range of the present invention is:0.25%~0.45%, preferred scope is 0.30%-0.40%.
V:Midium-carbon steel requirement is fine-grained steel, smaller than coarse-grained steel irradiation fragility.Add in steel Entering V has crystal grain thinning, improves grain coarsening temperature effect.Simultaneously more importantly in steel Plus after V, separating out second phase particles can play effectively brilliant during long-time SPWHT Boundary's " anchoring " is acted on, and delays the decline of intensity.Therefore V content scope of the present invention is 0.02%-0.05%, preferably control range are 0.02%-0.04%.
P:Irradiation test shows that P is very sensitive to radiation embrittlement, while P content is higher, Be also easy to aggravate the generation of center segregation and center porosity, therefore it is required that in steel P content it is more low more Good, P content control range of the present invention is≤0.012%.
S:S easily forms S compounds in steel and is mingled with, and reduces impact flexibility, influences welding performance, Aggravate the generation of the defect such as center segregation, loose, therefore S contents control range of the present invention simultaneously For≤0.008% ,≤0.002% is preferably controlled to.
Gas [H], [O]:Generally speaking, their performances to steel are harmful to, while can also increase Plus radiation embrittlement effect, it is desirable to their content will be reduced to floor level.The present invention [H], [O] content control range are [H]≤2.0ppm, [O]≤30ppm.
A kind of manufacture method of 550MPa grades of nuclear power voltage-stablizer equipment steel, including smelt, forge Make, roll, be heat-treated,
Smelt:Produced using electric furnace, die casting process, using outside LF stoves in smelting process Refining and VD applications of vacuum, qualified molten steel are cast into polygonal steel ingot;
Forging:The polygonal excessive fire time Stew of steel ingot warp is thick, pull out, the steel billet thickness that final production goes out 330-450mm, whole process initial forging temperature >=1180 DEG C, final forging temperature >=800 DEG C, forging Than >=6.0;
Rolling:Under billet heating temperature >=1100 DEG C, rolled plate thickness >=100mm, stagnation pressure Than >=2.5, average rolling pass deflection >=10%;
Heat treatment:Steel plate needs to carry out modifier treatment after rolling, it is ensured that even tissue, crystal grain is tiny, Performance is stable.
Hardening and tempering process is:
Quenching:900 DEG C ± 15 DEG C, soaking time:2-4min/mm, fully is incubated to ensure Uniform austenite structure is formed, water quenching is carried out immediately after until surface of steel plate temperature is down to Less than 100 DEG C.
Tempering:645 DEG C ± 15 DEG C, soaking time:1-3min/mm, fully is incubated to ensure Carbide Precipitation in steel, and form stable tempered sorbite tissue.
The beneficial effects of the present invention are:
Steel plate thickness >=100mm, width and length can be produced according to the actual requirements.With Prior art is compared, and is had the beneficial effect that (by taking 119mm plates as an example):
(1) steel plate of the present invention is respectively provided with preferable strength level after QT under different conditions:
It is strong at steel plate thickness 1/4 and at 1/2 from the point of view of QT and SPWHT two states Spend fall smaller and controllable, index request can be met completely.
(2) steel plate of the present invention is after QT, and -20 DEG C of impact absorbing energy under different conditions are same Higher level is maintained at, the requirement of index is not only met, and with larger surplus:
Brief description of the drawings
Fig. 1 is micro-organization chart at the quenched and tempered state thickness 1/4 of the embodiment of the present invention 1.
Fig. 2 is micro-organization chart at the Simulated post-weld heat treatment thickness 1/4 of the embodiment of the present invention 1.
Fig. 3 is micro-organization chart at the quenched and tempered state thickness 1/2 of the embodiment of the present invention 2.
Fig. 4 is micro-organization chart at the Simulated post-weld heat treatment state thickness 1/2 of the embodiment of the present invention 2.
Embodiment
Below by embodiment, the present invention is further illustrated.
The embodiment of the present invention according to the component proportion of technical scheme, smelted, forged, being rolled, Heat treatment.The composition of steel of the embodiment of the present invention is shown in Table 1.The forging technology of steel of the embodiment of the present invention Parameter is shown in Table 2.The rolling and heat treatment of steel of the embodiment of the present invention are shown in Table 3.The embodiment of the present invention Steel Properties are shown in Table 4.
The composition of the steel of the embodiment of the present invention of table 1 is shown in
The smithing technological parameter of the steel of the embodiment of the present invention of table 2
Embodiment Initial forging temperature/DEG C Final forging temperature/DEG C Finish-forging size (thickness)/mm Forging ratio
1 1200 840 350 9.44
2 1220 850 350 9.44
3 1250 910 400 8.26
4 1260 920 400 8.26
5 1230 920 420 7.86
6 1200 890 420 7.86
7 1250 930 450 6.86
8 1260 940 450 6.86
The rolling and heat treatment of the steel of the embodiment of the present invention of table 3
The Steel Properties of the embodiment of the present invention of table 4

Claims (2)

1. a kind of 550MPa grades of nuclear power voltage-stablizer equipment steel, it is characterised in that the steel plate into Divide as follows by weight percentage:C:0.10%~0.20%, Si:0.10%~0.40%, Mn:1.30%~1.60%, Mo:0.40~0.60%, Ni:0.60%~0.80%, Cr: 0.25%~0.45%, V:0.02%~0.05%, surplus is Fe and inevitable impurity. Impurity element control in steel:P≤0.012%, S≤0.008%, [H]≤2.0ppm, [O] ≤30ppm。
2. a kind of manufacturer of the 550MPa level nuclear power voltage-stablizer equipment steel described in claim 1 Method, including smelt, forge, roll, be heat-treated, it is characterised in that:
(1) smelt:Produced using electric furnace, die casting process, LF is used in smelting process External refining and VD applications of vacuum, are cast into polygonal steel ingot;
(2) forge:The polygonal excessive fire time Stew of steel ingot warp is thick, pull out, and the steel billet produced is thick Spend 330-450mm, forging process initial forging temperature >=1180 DEG C, final forging temperature >=800 DEG C, forging Make ratio >=6.0;
(3) roll:Billet heating temperature >=1100 DEG C, rolled plate thickness >=100mm, Ratio >=2.5 under stagnation pressure, average rolling pass deflection >=10%;
(4) it is heat-treated:Quenching:900 DEG C ± 15 DEG C, soaking time:2-4min/mm, Water quenching is carried out immediately after until surface of steel plate temperature is down to less than 100 DEG C, is tempered afterwards:645 DEG C ± 15 DEG C, soaking time:1-3min/mm.
CN201610203419.6A 2016-03-31 2016-03-31 A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method Pending CN107287509A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201610203419.6A CN107287509A (en) 2016-03-31 2016-03-31 A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201610203419.6A CN107287509A (en) 2016-03-31 2016-03-31 A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method

Publications (1)

Publication Number Publication Date
CN107287509A true CN107287509A (en) 2017-10-24

Family

ID=60088266

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201610203419.6A Pending CN107287509A (en) 2016-03-31 2016-03-31 A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method

Country Status (1)

Country Link
CN (1) CN107287509A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108385023A (en) * 2018-03-30 2018-08-10 鞍钢股份有限公司 A kind of high-strength and high ductility nuclear power voltage-stablizer steel and its manufacturing method
CN111020405A (en) * 2019-11-25 2020-04-17 鞍钢股份有限公司 High-strength steel plate for pressurized water reactor nuclear power station containment shell head and manufacturing method thereof
CN117226218A (en) * 2023-09-22 2023-12-15 东方法马通核泵有限责任公司 Build-up welding process of pressurized water reactor nuclear power coolant main pump

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101476088A (en) * 2008-12-31 2009-07-08 钢铁研究总院 R17Cr1Ni3Mo steel for nuclear pressure vessel and preparation thereof
CN102392195A (en) * 2011-12-15 2012-03-28 钢铁研究总院 High-strength high-toughness nuclear power pressure vessel forging steel and its manufacturing method
CN103160732A (en) * 2011-12-14 2013-06-19 鞍钢股份有限公司 Steel for nuclear power pressure-bearing equipment and manufacturing method thereof
CN103882333A (en) * 2012-12-21 2014-06-25 鞍钢股份有限公司 Steel for 620 MPa level nuclear first grade equipment and manufacturing method thereof
CN104561824A (en) * 2013-10-10 2015-04-29 鞍钢股份有限公司 Nuclear class equipment supporting steel and production method thereof
CN105506508A (en) * 2014-09-26 2016-04-20 鞍钢股份有限公司 Steel used for third-generation nuclear power safety injection tank base plate and manufacturing method of steel

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101476088A (en) * 2008-12-31 2009-07-08 钢铁研究总院 R17Cr1Ni3Mo steel for nuclear pressure vessel and preparation thereof
CN103160732A (en) * 2011-12-14 2013-06-19 鞍钢股份有限公司 Steel for nuclear power pressure-bearing equipment and manufacturing method thereof
CN102392195A (en) * 2011-12-15 2012-03-28 钢铁研究总院 High-strength high-toughness nuclear power pressure vessel forging steel and its manufacturing method
CN103882333A (en) * 2012-12-21 2014-06-25 鞍钢股份有限公司 Steel for 620 MPa level nuclear first grade equipment and manufacturing method thereof
CN104561824A (en) * 2013-10-10 2015-04-29 鞍钢股份有限公司 Nuclear class equipment supporting steel and production method thereof
CN105506508A (en) * 2014-09-26 2016-04-20 鞍钢股份有限公司 Steel used for third-generation nuclear power safety injection tank base plate and manufacturing method of steel

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108385023A (en) * 2018-03-30 2018-08-10 鞍钢股份有限公司 A kind of high-strength and high ductility nuclear power voltage-stablizer steel and its manufacturing method
CN111020405A (en) * 2019-11-25 2020-04-17 鞍钢股份有限公司 High-strength steel plate for pressurized water reactor nuclear power station containment shell head and manufacturing method thereof
CN117226218A (en) * 2023-09-22 2023-12-15 东方法马通核泵有限责任公司 Build-up welding process of pressurized water reactor nuclear power coolant main pump
CN117226218B (en) * 2023-09-22 2024-04-23 东方法马通核泵有限责任公司 Build-up welding process of pressurized water reactor nuclear power coolant main pump

Similar Documents

Publication Publication Date Title
CN103233183B (en) A kind of yield strength 960MPa grade super strength steel plate and manufacture method thereof
CN107988550B (en) Steel for pressurized water reactor nuclear power station pressure vessel support and manufacturing method thereof
CN105543704B (en) A kind of high-strength anti-seismic fire resisting corrosion resistant plate and manufacture method
CN104195458B (en) A kind of stainless steel hot-rolling plate of low relative permeability and preparation method thereof
CN101928885B (en) Hydrothion corrosion resistant pipe steel and production method thereof
CN109694988A (en) A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method
CN104694816A (en) Preparation method of high-Al medium manganese steel with strength and ductility product exceeding 30GPa%
CN108546878B (en) Steel for supporting thick nuclear power steam generator and production method thereof
CN105506508A (en) Steel used for third-generation nuclear power safety injection tank base plate and manufacturing method of steel
CN109136653A (en) For the nickel-base alloy of nuclear power generating equipment and its manufacturing method of hot rolled plate
CN109112423A (en) Special thick alloy-steel plate of a kind of superior low-temperature toughness and preparation method thereof
CN107287500A (en) A kind of pressurized-water reactor nuclear power plant safety injection tank substrate steel and its manufacture method
CN106480368A (en) One kind wards off rear high-strength hot rolled steel plate for counter enameling and its manufacture method
CN111020405A (en) High-strength steel plate for pressurized water reactor nuclear power station containment shell head and manufacturing method thereof
CN108359892A (en) A kind of the used in nuclear power station steel and its manufacturing method of bending forming function admirable
CN108385023A (en) A kind of high-strength and high ductility nuclear power voltage-stablizer steel and its manufacturing method
CN109182916A (en) A kind of wind-powered electricity generation high performance ultra-thick steel plate and its production method
CN108441779B (en) A kind of high intensity high-yield-ratio nuclear power station mechanical module steel and its manufacturing method
CN108950387A (en) With excellent high performance think gauge nuclear power safety injection tank steel and its manufacturing method
CN103045965A (en) Technique for manufacturing steel plate for 600MPa hydropower steel penstock
CN102628142B (en) Preparation method of low-activation steel for nuclear fusion
CN107287509A (en) A kind of 550MPa grades of nuclear power voltage-stablizer equipment steel and its manufacture method
CN114351058B (en) Alloy steel with yield strength of 2000MPa and preparation method thereof
CN103422027B (en) A kind of Economical low yield point steel and production method thereof
CN108165883A (en) 20crmnmo steel and its processing method

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
WD01 Invention patent application deemed withdrawn after publication

Application publication date: 20171024

WD01 Invention patent application deemed withdrawn after publication