CN109694988A - A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method - Google Patents
A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method Download PDFInfo
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/02—Ferrous alloys, e.g. steel alloys containing silicon
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- C—CHEMISTRY; METALLURGY
- C21—METALLURGY OF IRON
- C21C—PROCESSING OF PIG-IRON, e.g. REFINING, MANUFACTURE OF WROUGHT-IRON OR STEEL; TREATMENT IN MOLTEN STATE OF FERROUS ALLOYS
- C21C7/00—Treating molten ferrous alloys, e.g. steel, not covered by groups C21C1/00 - C21C5/00
- C21C7/10—Handling in a vacuum
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- C—CHEMISTRY; METALLURGY
- C21—METALLURGY OF IRON
- C21D—MODIFYING 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
- C21D1/00—General methods or devices for heat treatment, e.g. annealing, hardening, quenching or tempering
- C21D1/18—Hardening; Quenching with or without subsequent tempering
- C21D1/25—Hardening, combined with annealing between 300 degrees Celsius and 600 degrees Celsius, i.e. heat refining ("Vergüten")
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- C—CHEMISTRY; METALLURGY
- C21—METALLURGY OF IRON
- C21D—MODIFYING 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
- C21D8/00—Modifying the physical properties by deformation combined with, or followed by, heat treatment
- C21D8/02—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips
- C21D8/0221—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the working steps
- C21D8/0226—Hot rolling
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/04—Ferrous alloys, e.g. steel alloys containing manganese
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/42—Ferrous alloys, e.g. steel alloys containing chromium with nickel with copper
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/44—Ferrous alloys, e.g. steel alloys containing chromium with nickel with molybdenum or tungsten
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/46—Ferrous alloys, e.g. steel alloys containing chromium with nickel with vanadium
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/50—Ferrous alloys, e.g. steel alloys containing chromium with nickel with titanium or zirconium
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
- C22C38/54—Ferrous alloys, e.g. steel alloys containing chromium with nickel with boron
Abstract
The present invention discloses a kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method.Contain C:0.10%~0.17%, Si:0.25%~0.35%, Mn:0.45%~0.90%, P≤0.015%, S≤0.003%, Ni:0.20%~0.45%, Cr:0.90%~1.10%, Mo:0.30%~0.50%, Ti:0.01%~0.03%, V:0.01%~0.03%, Cu:0.1%~0.3%, B:0.001%~0.005% in steel, remaining is Fe and inevitable impurity.1580~1610 DEG C of vacuum outgas, the degree of superheat >=50 DEG C, drawing speed > 1.5m/min；1100~1150 DEG C of slab heating temperature, start rolling temperature >=1000 DEG C, 880~920 DEG C of finishing temperature；890~920 DEG C of hardening heat, 2.5~4.5min/mm of soaking time；620~650 DEG C of tempering temperature, 2~4min/mm of soaking time.Product is used for three generations's pressurized-water reactor nuclear power plant suspension and support, low-temperature flexibility and good strength.
Description
Technical field
The invention belongs to nuclear power generating equipment steel making fields, are related specifically to a kind of three generations's pressurized-water reactor nuclear power plant suspension and support use
Steel and its manufacturing method.
Background technique
Nuclear leve suspension and support is an important component of nuclear power station, and nuclear power station design is very high to security requirement, and branch is hung
Design, manufacture and the installation of frame will consider destruction caused by seismic (seismal.Therefore, the design of nuclear leve pipe-hanger support,
Whether manufacture, installation are reasonable, it directly affects the operational reliability of nuclear power station, influences construction of nuclear power station period and investment.
At abroad, since nuclear power station development is very fast, so the specification of its suspension and support, type, the scope of application are more comprehensive.State
Wai Ji great nuclear power generating equipment manufacturer manufactures nuclear leve pipe-hanger support for a long time, and product seriation standardizes, technology maturation, greatly
Amount is applied in design, construction and the maintenance of each nuclear power plant, but China is built and hangs in many nuclear leve pipeline branch of nuclear power station built
Frame uses imported product, and three generations's pressurized-water reactor nuclear power plant unit is advanced in digestion, absorption, comprehensive third generation for grasping China's introduction
On the basis of nuclear power AP1000 passive technology, China's independent intellectual property right, more powerful is provided by innovative development again
Passive large size advanced pressurized water reactor nuclear power unit, and the nuclear leve pipe-hanger support of nuclear power plant forms the body of production domesticization completely not yet
System and standard, manufacturer are short in understanding to nuclear power specification.With greatly developing for China's Nuclear Electricity, nuclear power product market prospects
Wide, following developing direction should be the standard to form a set of nuclear power station-service nuclear leve pipe-hanger support in line with international standards, be
Column, to meet the production domesticization needs of nuclear power station.
Suspension and support mainly includes transversal force suspension and support, spring support hanging frame, pipe portion part, connector and root bearing etc. in nuclear power station
Supporting portion, pipe-hanger support more than totally three ten thousand according to statistics, in every three generations's pressurized-water reactor nuclear power plant unit, pipe portion part is occupied absolutely
Most of, so matched suspension and support is very big with steel requirement, the steel grade needed is also complex.Due to pressing three generations
Water-water reactor nuclear power station unit station security requirement is higher and the installed capacity of nuclear power unit increases increasingly, to three generations's compressed water reactor nuclear power
Standing, higher requirements are also raised for unit suspension and support steel.
More patent has been formed to midium-carbon steel both at home and abroad at present:
CN 201510765103.1 discloses a kind of production technology of suspension and support with cracking resistance corrosion resistance, is related to
A kind of steel manufacturing process that forging rolling combines, selects the mass percent of alloy blank chemical component are as follows: and Cr:28.0%~
29.0%, Ni:2.1%~3.3%, C≤0.05%, Mo:3.0%~5.0%, Cu:0.52%~0.54%, Si:0.89%
~0.93%, Nb:0.14%~0.16%, Ti:0.097%~0.099%, Ca:0.15%~0.17%, Se:0.05%~
0.15%, Te:0.15%~0.19%, S:0.015%~0.025%, P:0.021%~0.023%, lanthanide rare: 5.5%
~6.6%, remaining is Fe and inevitable impurity；The steel grade is stainless steel, in addition, its manufacturing method is forging-heat treatment-machine
Tool roughing-surface coats production technology, not only plus increases cost but also increases the production cycle.
CN201510312965.9 discloses a kind of anti-corrosion and high strength suspension and support component and its manufacturing process, production method
Include the steps that it is following successively: rolling: roughing temperature be 1270~1290 DEG C, final rolling temperature be 960~980 DEG C, finishing temperature
It is 830~850 DEG C, it is first cold using oil after hot rolling, steel plate is cooled to 580~620 DEG C with the cooling rate of 10~12 DEG C/s, then
Using air-cooled, steel plate is cooled to 330~350 DEG C with the cooling rate of 6~8 DEG C/s, uses water cooling, finally with 3~6 DEG C/s's
Steel plate is cooled to room temperature by cooling rate；The rolling mill practice that controlled rolling and controlled cooling is used in the patent, is respectively adopted wherein controlling cold process
Oily cold, air-cooled and three kinds of types of cooling of water cooling, complex process.
CN201510764113.3 discloses a kind of production technology of pressure-resistant corrosion-resisting suspension and support suitable for low temperature environment,
The production of pressure-resistant corrosion-resisting suspension and support suitable for low temperature environment, which is characterized in that three-stage solid solution heat is carried out using bell furnace
Processing, specifically: first segment heating temperature is 700~750 DEG C, keeps the temperature 10~15min after arriving temperature, second segment heating temperature is
850~880 DEG C, to temperature after keep the temperature 35~40min, third section heating temperature be 1010~1150 DEG C, to temperature after heat preservation 15~
18min；Control cooling velocity is 5.5~6 DEG C/s when cooling, guarantees that forging can be cooled to 40 DEG C in 3 minutes；The present invention is raw
The suspension and support of production, tensile strength >=520MPa；Extend >=38%；Brinell hardness 180 >=HB >=140；- 196 DEG C of ballistic works: horizontal
It is greater than 0.38mm to side swell increment；Meanwhile the performance with good intergranular corrosion resistance, while the coating in the present invention is with good
Good adhesive force, gained coating have excellent impact strength and wearability.The invention Three-section type heating system is complicated, and steel
The tensile strength of plate is lower.
Summary of the invention
The present invention provides a kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method, by closing in smelting process
The design of gold element, the setting of continuous casting process, and suitable heat treatment process is formulated, make steel plate in condition of heat treatment, simulation weldering
The mechanical property of condition of heat treatment and 360 DEG C of conditions of high temperature keeps higher level afterwards, fully meets the requirement of technical indicator, steel
The plate Z-direction contraction percentage of area is >=35%；- 18 DEG C of impact absorbing energy remain at higher level simultaneously, embody preferable
The matching of armor plate strength and toughness is fully able to meet the requirement of three generations's pressurized-water reactor nuclear power plant suspension and support steel.
Specific technical solution is:
A kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel, chemical component is by weight percentage are as follows: and C:0.10%~
0.17%, Si:0.25%~0.35%, Mn:0.45%~0.90%, P≤0.015%, S≤0.003%, Ni:0.20%~
0.45%, Cr:0.90%~1.10%, Mo:0.30%~0.50%, Ti:0.01%~0.03%, V:0.01%~
0.03%, Cu:0.1%~0.3%, B:0.001%~0.005%, remaining content are Fe and inevitable impurity.
It is as follows using mentioned component design reason:
C:C is the main component of steel grade, and with the increase of C content, the yield strength and tensile strength of steel, which can correspond to, to be mentioned
Height, but the Carbide Precipitation that too low C element content will lead to after being heat-treated in steel is reduced, and causes the strong of Simulated post-weld heat treatment
Degree and toughness are lower.The matching of superperformance is all had to guarantee steel plate in various states, therefore the present invention claims C in steel to contain
Amount preferably controls in 0.10%~0.17% range.
Si:Si is effective intensified element, and especially in quenched structural steel, a certain amount of Si element, which is added, significantly to be mentioned
The yield strength and tensile strength of Gao Gang, but the Si element of too high amount can reduce welding performance, therefore the Si content of this patent
Control is 0.25%~0.35%.
Mn:Mn element steel grade can by way of solution strengthening reinforced ferrite, steel can be improved in quenched and tempered steel
Obdurability and harden ability, therefore in the present invention Mn content control 0.45%~0.90%.
P: P element can improve the sensibility of neutron-irradiation-induced embrittlement in midium-carbon steel, and increasing for P element can serious shadow
The center portion quality of castanets base, therefore it is required that the lower P content in steel the better, the present invention, which controls P content, is being lower than 0.015%.
S:S usually easily forms brittle sulfide with the alloying element in steel, so that steel is generated red brittleness, reduces the ductility of steel
And toughness, while S also has the tendency that accelerating radiation embrittlement, excessively high S element be easy to cause segregation in the steel billet center portion solidification later period,
Seriously affect the Z-direction performance of steel billet.Therefore the present invention claims S contents in steel to be limited in 0.003% or less.
Ni:Ni element can be improved the intensity of steel and can be obviously improved the low-temperature flexibility of steel, especially to think gauge steel
The toughness of plate can play guaranteeing role, it is contemplated that the nuclear power steel plate of the patented invention also has the toughness of Simulated post-weld heat treatment
Higher requirement, therefore the present invention controls Ni content 0.20%~0.45%.
Cr:Cr element can significantly improve intensity, hardness and wearability in structural steel, can improve the anti-of steel in steel
Oxidation increases resistance to corrosion, and Cr can be improved certain harden ability, but Cr too high levels, will increase the weldering of steel
Crack sensitivity afterwards, therefore be 0.90%~1.10% the present invention claims Cr content control in steel.
Mo:Mo can make the crystal grain refinement of steel, improve harden ability and thermostrength, and it is enough can to guarantee that steel has at high temperature
Intensity and creep resisting ability, molybdenum is added in structural steel, mechanical performance can be improved, therefore the present invention claims Mo contents in steel to control
It is 0.30%~0.50%.
V, Ti:V and Ti belongs to microalloy element, and V and Ti is capable of forming tiny second phase particles in steel, plays pinning crystalline substance
The effect on boundary and precipitation strength can effectively refine crystal grain, especially improve the elevated temperature strength of steel, therefore V, Ti are added in steel
Range be 0.010%~0.030%.
Cu:Cu can improve intensity and toughness, especially utilize the precipitation strength center portion intensity and toughness of copper.The disadvantage is that
Be easy to produce when hot-working it is hot-short, therefore the present invention claims in steel Cu content control be 0.1%~0.3%.
B:B element is unique intergranular intensified element, and micro boron is added in steel can improve the compactness and hot rolling of steel
Performance improves intensity.Therefore the additional amount of B is controlled 0.001%~0.005% in the present invention.
The present invention also provides a kind of manufacturing method of three generations's pressurized-water reactor nuclear power plant suspension and support steel, including converter smelting,
External refining, continuous casting, rolling, heat treatment.Its main technique are as follows:
Smelt aspect: molten steel carries out external refining after completing converter smelting, it is ensured that in steel [S]≤0.003%, [P]≤
0.015%；Fruit storage is carried out when molten steel completes external refining and reaches 1580~1610 DEG C, guarantees that gas contains in steel
Amount enters continuous casting after completing vacuum outgas by [H]≤2.0ppm, [O]≤20ppm, [N]≤50ppm control.
In terms of continuous casting: continuous casting process need to guarantee molten steel overheat >=50 DEG C, weak cold and continuous casting drawing speed > 1.5m/min,
It can guarantee that column trichite reaches in continuous casting billet, the generation of center portion equiax crystal be reduced, because carbide is in continuous casting billet solidification processing
Easily assemble in the intersection of column crystal and equiax crystal, this phenomenon will lead to toughness reduction, while the reduction of equiax crystal is certain
Center segregation degree can be reduced in degree, and the steel plate Z-direction performance after rolling is also improved.
Rolling aspect: 1100~1150 DEG C of continuous blank heating temperature, start rolling temperature >=1000 DEG C, finishing temperature 880~920
℃。
It is higher to burn the lower intensity for rolling state steel plate of steel temperature in certain temperature range for the burning steel temperature for controlling continuous casting billet；
The purpose of normalizing rolling can be played by controlling lower finishing temperature, guarantees further refinement original austenite grains ruler
It is very little.
Heat treatment: hardening heat: 890~920 DEG C, soaking time: 2.5~4.5min/mm；Tempering temperature: 620~650
DEG C, soaking time: 2~4min/mm.
Cu-Cr alloy can form the martensitic structure of high density dislocation, highdensity dislocation and refinement in quenching process
Crystal grain can be respectively increased the toughness and intensity of steel plate；Cr, Mo element can be sufficiently dissolved in quenching, in drawing process
In, Cr and Mo element is strong carboritride, and a large amount of carboritride can be precipitated, and can be improved the intensity and toughness of steel plate.
The utility model has the advantages that
The present invention provides three generations's pressurized-water reactor nuclear power plant suspension and support steel and its manufacturing method, the steel plate thickness of production is 20
~80mm compared with the existing technology has the beneficial effect that:
(1) it is column crystal inside continuous casting billet by the control to continuous casting process, does not generate taking for column crystal and equiax crystal
Boundary avoids carbide and easily assembles in the intersection of column crystal and equiax crystal in continuous casting billet solidification processing, guarantees steel plate thickness
Low-temperature flexibility at 1/4, -18 DEG C impact absorbing energy of the steel plate under different conditions are equally maintained at higher level.50mm
Impact absorbing energy after plate modifier treatment and Simulated post-weld heat treatment is respectively 135J and 150J or so, not only meets index
It is required that and there is biggish surplus.
(2) after conditioned processing, preferable strength level is all had under different conditions.It is bent after the conditioned processing of 50mm steel plate
It takes intensity and tensile strength is respectively 843MPa and 892MPa；After Simulated post-weld heat treatment, yield strength and tensile strength difference
For 809MPa and 844MPa (index request yield strength >=620MPa, tensile strength: 725~930MPa), from the results of view, steel
Plate intensity fall is smaller, and different conditions can satisfy index request, has compared with other steel grades and significantly improves.
(3) the finished steel plate Z-direction contraction percentage of area produced is all satisfied the requirement greater than 35%.
Detailed description of the invention
Fig. 1 is the arborescent structure of continuous casting billet, and Fig. 2 is the metallographic structure of each 1 quality adjustment condition of embodiment.Wherein, the company in Fig. 1
It is column crystal inside slab；Tissue in Fig. 2 is tempered sorbite.
Specific embodiment
For following embodiment for illustrating the content of present invention, these embodiments are only the general description of the content of present invention,
The content of present invention is not limited.
Table 1 is the smelting chemical ingredient of embodiment steel；2 steel-making continuous casting data of table；Table 3 is at the rolling and heat of embodiment steel
Science and engineering skill；Table 4 is the mechanical property of embodiment steel plate.
The production method of the present embodiment steel is using low P, low S molten iron as raw material, and molten steel passes through converter smelting, LF+VD furnace
Outer refining pours into continuous casting billet, and mill product steel plate specification is 20~80mm, Simulated post-weld heat treatment technique be temperature 605 ±
10 DEG C, soaking time 10h, 425 DEG C or more temperature rate≤55 DEG C/h.
1 embodiment steel smelting chemical component (%) of table
| Embodiment | C | Si | Mn | P | S | Ni | Cr | Mo | V | Cu | B | Ti |
| 1 | 0.11 | 0.24 | 0.51 | 0.011 | 0.002 | 0.21 | 0.92 | 0.45 | 0.017 | 0.12 | 0.0017 | 0.011 |
| 2 | 0.12 | 0.25 | 0.53 | 0.010 | 0.001 | 0.28 | 1.00 | 0.47 | 0.019 | 0.22 | 0.0019 | 0.012 |
| 3 | 0.15 | 0.26 | 0.50 | 0.008 | 0.002 | 0.25 | 0.90 | 0.49 | 0.018 | 0.19 | 0.0020 | 0.021 |
| 4 | 0.16 | 0.35 | 0.49 | 0.010 | 0.002 | 0.33 | 0.92 | 0.37 | 0.012 | 0.15 | 0.0027 | 0.014 |
| 5 | 0.17 | 0.28 | 0.47 | 0.010 | 0.001 | 0.30 | 0.95 | 0.41 | 0.025 | 0.17 | 0.0023 | 0.013 |
| 6 | 0.13 | 0.30 | 0.55 | 0.011 | 0.002 | 0.27 | 0.93 | 0.50 | 0.021 | 0.20 | 0.0035 | 0.015 |
Note: [H]≤2.0ppm, [O]≤20ppm, [N]≤50ppm in molten steel.
2 steel-making continuous casting data of table
The rolling and heat treatment process of 3 embodiment steel of table
The mechanical property of 4 embodiment steel plate of table
20~80mm specification steel plate passes through modifier treatment and Simulated post-weld heat treatment, and performance indexes, which is fully met, to be wanted
It asks, steel plate has good comprehensive mechanical property.
Claims (2)
1. a kind of three generations's pressurized-water reactor nuclear power plant suspension and support steel, which is characterized in that chemical component is by mass percentage in steel are as follows: C:
0.10%~0.17%, Si:0.25%~0.35%, Mn:0.45%~0.90%, P≤0.015%, S≤0.003%, Ni:
0.20%~0.45%, Cr:0.90%~1.10%, Mo:0.30%~0.50%, Ti:0.01%~0.03%, V:0.01%
~0.03%, Cu:0.1%~0.3%, B:0.001%~0.005%, remaining is Fe and inevitable impurity.
2. a kind of manufacturing method of three generations's pressurized-water reactor nuclear power plant suspension and support steel as described in claim 1, the production work of steel plate
Skill are as follows: converter smelting, external refining, continuous casting, rolling, heat treatment, which is characterized in that
Smelt: molten steel carries out external refining after completing converter smelting, it is ensured that S≤0.003% in steel, P≤0.015%；Work as molten steel
Complete external refining and while reaching 1580~1610 DEG C carry out Fruit storage, guarantee in steel gas content by [H]≤
2.0ppm, [O]≤20ppm, [N]≤50ppm control, enter continuous casting after vacuum outgas；
Continuous casting: continuous casting process need to guarantee molten steel overheat >=50 DEG C, weak cold and continuous casting drawing speed > 1.5m/min；
Rolling: 1100~1150 DEG C of continuous blank heating temperature, start rolling temperature >=1000 DEG C, 880~920 DEG C of finishing temperature；
Heat treatment: hardening heat: 890~920 DEG C, soaking time: 2.5~4.5min/mm；Tempering temperature: it 620~650 DEG C, protects
The warm time: 2~4min/mm.
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| CN111270144A (en) * | 2020-03-19 | 2020-06-12 | 鞍钢股份有限公司 | High-strength steel plate for pressurized water reactor nuclear power station safety shell barrel and manufacturing method thereof |
| CN111270143A (en) * | 2020-03-19 | 2020-06-12 | 鞍钢股份有限公司 | Thick steel plate for nuclear power station containment equipment module and production method thereof |
| CN111363985A (en) * | 2020-03-19 | 2020-07-03 | 鞍钢股份有限公司 | Steel for supporting nuclear power station containment vessel and manufacturing method thereof |
| CN111394547A (en) * | 2020-03-19 | 2020-07-10 | 鞍钢股份有限公司 | Ultra-thick high-strength steel for nuclear reactor containment vessel and manufacturing method thereof |
| CN111394651A (en) * | 2020-03-31 | 2020-07-10 | 湖南华菱湘潭钢铁有限公司 | Atmospheric corrosion resistant steel for nuclear power heavy-duty supporting equipment and production method thereof |
| CN112063935A (en) * | 2020-09-25 | 2020-12-11 | 湖南华菱湘潭钢铁有限公司 | Production method of steel for nuclear grade support and hanger of CAP (capacitor CAP) passive nuclear power plant |
| CN112126861A (en) * | 2020-09-25 | 2020-12-25 | 湖南华菱湘潭钢铁有限公司 | Production method of high-strength and high-toughness steel for CAP nuclear power plant nuclear-grade mechanical module |
| CN112941413A (en) * | 2021-02-01 | 2021-06-11 | 南京理工大学 | Anti-irradiation nuclear power reactor pressure vessel alloy |
| CN116145030A (en) * | 2022-12-23 | 2023-05-23 | 鞍钢股份有限公司 | Ferrite stainless steel plate for supporting key equipment of third-generation nuclear power station and manufacturing method |
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| CN116145030A (en) * | 2022-12-23 | 2023-05-23 | 鞍钢股份有限公司 | Ferrite stainless steel plate for supporting key equipment of third-generation nuclear power station and manufacturing method |
| CN116145030B (en) * | 2022-12-23 | 2023-12-15 | 鞍钢股份有限公司 | Ferrite stainless steel plate for supporting key equipment of third-generation nuclear power station and manufacturing method |
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