CN102400058A - Steel for nuclear reactor containment vessel head and cylinder - Google Patents
Steel for nuclear reactor containment vessel head and cylinder Download PDFInfo
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- CN102400058A CN102400058A CN2010102765029A CN201010276502A CN102400058A CN 102400058 A CN102400058 A CN 102400058A CN 2010102765029 A CN2010102765029 A CN 2010102765029A CN 201010276502 A CN201010276502 A CN 201010276502A CN 102400058 A CN102400058 A CN 102400058A
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- 229910000831 Steel Inorganic materials 0.000 title claims abstract description 114
- 239000010959 steel Substances 0.000 title claims abstract description 114
- 229910052799 carbon Inorganic materials 0.000 claims abstract description 21
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 14
- 229910052717 sulfur Inorganic materials 0.000 claims abstract description 9
- 239000012535 impurity Substances 0.000 claims abstract description 8
- 229910052750 molybdenum Inorganic materials 0.000 claims abstract description 7
- 239000000126 substance Substances 0.000 claims abstract description 4
- 238000004364 calculation method Methods 0.000 claims abstract description 3
- 229910052758 niobium Inorganic materials 0.000 claims description 9
- 229910052698 phosphorus Inorganic materials 0.000 claims description 8
- 229910052720 vanadium Inorganic materials 0.000 claims description 8
- 229910052804 chromium Inorganic materials 0.000 claims description 7
- 229910052802 copper Inorganic materials 0.000 claims description 7
- 229910052759 nickel Inorganic materials 0.000 claims description 6
- 239000004615 ingredient Substances 0.000 claims 1
- 229910052748 manganese Inorganic materials 0.000 abstract description 6
- 238000010521 absorption reaction Methods 0.000 description 11
- 230000035939 shock Effects 0.000 description 11
- 239000003607 modifier Substances 0.000 description 8
- 230000000694 effects Effects 0.000 description 6
- 238000004519 manufacturing process Methods 0.000 description 6
- 238000003723 Smelting Methods 0.000 description 5
- 238000009749 continuous casting Methods 0.000 description 5
- 238000005516 engineering process Methods 0.000 description 5
- 238000009413 insulation Methods 0.000 description 5
- 238000007670 refining Methods 0.000 description 5
- 230000005855 radiation Effects 0.000 description 4
- 238000000034 method Methods 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 2
- 238000005204 segregation Methods 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- CWYNVVGOOAEACU-UHFFFAOYSA-N Fe2+ Chemical compound [Fe+2] CWYNVVGOOAEACU-UHFFFAOYSA-N 0.000 description 1
- 229910001566 austenite Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000002939 deleterious effect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 201000007094 prostatitis Diseases 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000005728 strengthening Methods 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Landscapes
- Treatment Of Steel In Its Molten State (AREA)
Abstract
The invention discloses steel for a nuclear reactor containment shell head and a shell, which comprises the following chemical components in percentage by weight: c is less than or equal to 0.20 percent; 0.15% -0.55% of Si; 0.90-1.60% Mn; p is less than or equal to 0.025 percent; less than or equal to 0.025 percent of S; ni less than or equal to 0.60 percent; cr is less than or equal to 0.30 percent; less than or equal to 0.30 percent of Mo; nb of less than or equal to 0.04 percent; v is less than or equal to 0.07 percent; cu of less than or equal to 0.35 percent, V + Nb of less than or equal to 0.08 percent, the balance of Fe and inevitable impurities, the carbon equivalent in the steel is 0.40 to 0.44 percent, and the carbon equivalent calculation formula CE is C + Mn/6+ (Cr + Mo + V)/5+ (Ni + Cu)/15, thereby controlling non-metallic inclusions in the steel, wherein A, B, C, D type inclusions are less than or equal to 1.5 grade. The invention effectively ensures that the steel plate has higher strength and uniform and stable toughness, particularly after long-time stress relief treatment, the strength of the steel plate can not be obviously reduced, and the index requirement can still be met.
Description
Technical field
The invention belongs to ferrous material, particularly the steel containment vessel end socket and the cylindrical shell of nuclear power plant equipment are used steel.
Background technology
Nuclear energy is accepted by countries in the world and exploitation energetically as a kind of economy, safety, cleaning, high efficient energy sources gradually.China has accelerated the dynamics of nuclear power exploitation especially since 2005, up to the present reached 28 at all kinds of million kilowatt nuclear power units of building, and becomes in the world and is building the maximum country of nuclear power generating sets.In numerous million kilowatt nuclear power units; Non-active third generation nuclear power technology---the large-scale advanced pressurized water reactor of AP1000 that China introduces from US Westinghouse company; Being not only nuclear power technology comparatively advanced on the our times, also is simultaneously that the Future in China nuclear power generating sets are built and Development Trend.
The reactor steel containment vessel is the exclusive safety precaution facility of AP1000 technology.Main effect comprises two aspects: the one, and the major equipment as containing the band radioactive substance can prevent that radioactive substance is to external diffusion; The 2nd, belong to the major equipment of AP1000 non-passive safety shell cooling system, be the important assurance of temperature in the control nuclear island.Compared with developed countries; Though China's nuclear power developing process is slow relatively; But going to prostatitis, the world aspect the introduction of AP1000 advanced pressurized water reactor and the construction, therefore aspect the production of steel and manufacturing technology, having no experience to follow at its distinctive reactor containment end socket and cylindrical shell.This steel grade performance requriements is not only comprehensive but also strict simultaneously: existing normal temperature, low-temperature performance requirement, also to carry out the high-temperature behavior check; Should check the performance after the steel plate modifier treatment, it is stable to guarantee that also long-time stress-removal is handled the back property retention; Taking into account armor plate strength, toughness simultaneously, also to have good welding property in addition, this also be reactor containment end socket and cylindrical shell the most key with steel also be the bigger controlling unit of difficulty.From the actual production technology, do not see the relevant report of similar research both at home and abroad at present as yet simultaneously.
Nuclear reactor safety shell end socket and cylindrical shell have only minority steel mill to produce with steel at present at home; And mainly have following two aspect problems in the actual production process: the one, through after reaching stress-removal more than 10 hours and handling; Armor plate strength obviously descends, and especially tensile strength has been lower than index request; The 2nd, the impelling strength of steel plate is inhomogeneous, and impact value is discrete, fluctuation is big, thereby causes the final properties percent of pass of steel plate to descend.The major cause one that produces the problems referred to above is in process of production, owing to pursue the welding property of steel plate excessively carbon equivalent is controlled at below 0.39%; The 2nd, in the actual production process, gas and non-metallic inclusion content are not reduced fully in the steel, thereby make the impelling strength of steel plate take place discrete.
Summary of the invention
The invention provides a kind of nuclear reactor safety shell end socket and cylindrical shell and use steel; Through reasonably controlling carbon equivalent in the steel, reducing gas and non-metallic inclusion content in the steel; Can guarantee effectively that steel plate has higher-strength simultaneously, also have even, stable toughness, especially after handling through long-time stress-removal; The intensity of steel plate can obviously not descended, and still can satisfy index request.
The objective of the invention is to realize like this, a kind of nuclear reactor safety shell end socket and cylindrical shell are used steel, and its chemical component weight per-cent is :≤0.20% C; The Si of 0.15%-0.55%; The Mn of 0.90%-1.60%; ≤0.025% P; ≤0.025% S; ≤0.60% Ni; ≤0.30% Cr; ≤0.30% Mo; ≤0.04% Nb; ≤0.07% V; ≤0.35% Cu requires V+Nb≤0.08% simultaneously, and all the other content are Fe and inevitable impurity.
In the mentioned component in the emphasis control steel carbon equivalent be 0.40%-0.44%.
Carbon equivalent calculation formula CE=C+Mn/6+ (Cr+Mo+V)/5+ (Ni+Cu)/15, down together.
Control nonmetallic inclusionsin steel simultaneously, guarantee that A, B, C, D class are mingled with≤1.5 grades (A tests by the ASTME45 method, down together).
Adopt the mentioned component design the reasons are as follows:
(1) C: C content is the principal element that guarantees armor plate strength in the steel, and C content is on the low side, and intensity has satisfied not requirement, and C content can improve radiation embrittlement property simultaneously greater than the weldability of 0.20% meeting reduction steel.Therefore the present invention requires C content≤0.20% in the steel, and optimum controling range is 0.07%-0.14%.
(2) Si:Si is a strengthening element, but the high irradiation fragility that increases of Si, so should be controlled at lower bound to Si content for well.The present invention requires Si content≤0.55% in the steel, and optimum controling range is 0.20%-0.40%.
(3) Mn: the Mn element is strengthened the matrix effect except plaing in the steel, can also improve the hardening capacity of steel effectively, but Mn content has the grain coarsening tendency that makes steel, and increases temper embrittlement susceptibility when higher.Therefore the present invention requires that Mn content is controlled at 0.80%-1.50% in the steel, and optimum controling range is 1.20%-1.50%.
(4) Ni:Ni can obviously improve the low-temperature flexibility of steel; Improve the hardening capacity of thick cross section steel plate simultaneously, but, reduce the A3 temperature of steel because Ni is the element that enlarges the γ phase; Therefore under the thermal stresses effect, lattice distortion is increased; Irradiation effect is bigger, so the present invention requires Ni content≤0.60% in the steel, and optimum controling range is 0.35%-0.55%.
(5) Cr:Cr can significantly improve the antioxygenation of steel in steel, increases resistance to corrosion.Dwindle the austenite phase region simultaneously, improve the through hardening performance of steel.But Cr also can significantly improve the brittle transition temperature of steel, promotes temper brittleness, so the present invention requires Cr content≤0.35% in the steel, and optimum controling range is 0.10%-0.20%.
(6) Mo: main effect is to improve thermotolerance and reduce temper brittleness, and the present invention requires Mo content≤0.30 in the steel, and optimum controling range is 0.10%-0.30%.
(7) V, Nb: it is fine grained steel that nuclear power requires with steel.Fine grained steel is littler than coarse-grained steel irradiation fragility; Adding V or Nb in the steel all has crystal grain thinning, improves the grain coarsening temperature; Therefore the present invention requires V content≤0.07% in the steel, Nb content≤0.05%, and optimum controling range is respectively 0.02%-0.06% and 0.01%-0.03%.
(8) Cu:Cu is to the most deleterious element of radiation embrittlement, and the present invention requires Cu content≤0.10% in the steel.
(9) P: irradiation test shows that P is also very responsive to radiation embrittlement, and P content is higher simultaneously, also is easy in steel, aggravate the generation of center segregation and center porosity, therefore requires the P content in the steel low more good more, and the present invention requires P content≤0.012%.
(10) S:S forms the Sization thing and is mingled with in steel, has reduced the impelling strength of steel, influences welding property, aggravate center segregation, generation of defects such as loose simultaneously, so the present invention requires S content≤0.003% in the steel.
(11) gas N, H, O: generally speaking, they are all harmful to the performance of steel, also can increase the radiation embrittlement effect simultaneously, therefore hope to be reduced to minimum level to their content.The present invention requires H≤1.5ppm in the steel, O≤30ppm, N≤60ppm.
A kind of nuclear reactor safety shell end socket provided by the invention and cylindrical shell are used steel plate, and thickness is at 40-50mm, and width and length can be produced according to the actual requirements.Compared with prior art, beneficial effect is following:
The one, in the control steel carbon equivalent at 0.40%-0.44%, can guarantee effectively after the steel plate modifier treatment ys at 480-540MPa, tensile strength 620-670MPa (press ASTM A370 check, down with); Steel plate after the modifier treatment again through 593-620 ℃, reach 10 hours stress-removal and handle after; Its intensity slightly descends; But average yield strength about 600MPa, satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell at 470MPa, average tensile strength fully.
The 2nd, after modifier treatment, steel plate shock absorption energy (45 ℃) basic controlling is 270-380J (pressing ASTM A370 check, down together), and is comparatively even, stable, satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell equally.
Embodiment
Embodiment one
The nuclear reactor safety shell end socket and the cylindrical shell of present embodiment are used steel, comprise following component by weight percentage: 0.07% C; 0.45% Si; 1.50% Mn; 0.010% P; The Ni of 0.0015% S:0.45%; The Mo of 0.17% Cr:0.16%; 0.02% Nb; 0.04% V; 0.01% Cu, all the other content are Fe and inevitable impurity.It is the 300mm strand that continuous casting becomes thickness, finally is rolled into the 42mm Plate Steel.
Press mentioned component, carbon equivalent (CE) is: 0.42%
Molten steel is handled gas content in the steel: [H] 1.0ppm, [O] 25ppm, [N] 55ppm through converter smelting, external refining (LF, VD) simultaneously.
Nonmetallic inclusionsin steel is: category-A＜0.5 grade, category-B＜0.5 grade, 0.5 grade of C class, 1.0 grades of D classes.
The nuclear reactor safety shell end socket of present embodiment and cylindrical shell with steel plate after modifier treatment; Stretch and the impact property check; The average yield strength of steel plate is that 515MPa, average tensile strength are that 635MPa, shock absorption energy (45 ℃) are controlled at 290-320J, average out to 308J; Steel plate is again after 620 ℃, 10 hours stress-removal of insulation are handled; Its ys and tensile strength slightly descend to some extent; Average yield strength slightly improves at 605MPa, shock absorption energy (45 ℃) at 480MPa, average tensile strength; Basically at 305-350J, average out to 339J satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell fully.
Embodiment two
The nuclear reactor safety shell end socket and the cylindrical shell of present embodiment are used steel, comprise following component by weight percentage: 0.07% C; 0.45% Si; 1.35% Mn; 0.010% P; 0.0015% S; 0.45% Ni; 0.18% Cr; 0.15% Mo; 0.02% Nb; 0.04% V; 0.01% Cu, all the other content are Fe and inevitable impurity.It is the 300mm strand that continuous casting becomes thickness, finally is rolled into the 42mm Plate Steel.
Press mentioned component, carbon equivalent (CE) is: 0.40%
Molten steel is handled gas content in the steel: [H] 1.5ppm, [O] 28ppm, [N] 57ppm through converter smelting, external refining (LF, VD) simultaneously.
Nonmetallic inclusionsin steel is: category-A＜0.5 grade, 0.5 grade of category-B, 0.5 grade of C class, 1.0 grades of D classes.
The nuclear reactor safety shell end socket of present embodiment and cylindrical shell with steel plate after modifier treatment; Stretch and the impact property check; The average yield strength of steel plate is that 500MPa, average tensile strength are that 620MPa, shock absorption energy (45 ℃) are controlled at 310-380J, average out to 350J; Steel plate is again after 620 ℃, 10 hours stress-removal of insulation are handled; Its ys and tensile strength slightly descend to some extent; Average yield strength at 470MPa, average tensile strength at 590MPa, shock absorption energy (45 ℃) basically at 320-370J; Average out to 345J satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell.
Embodiment three
The nuclear reactor safety shell end socket and the cylindrical shell of present embodiment are used steel, comprise following component by weight percentage: 0.10% C; 0.35% Si; 1.30% Mn; 0.010% P; 0.001% S; 0.46% Ni; 0.15% Cr; 0.14% Mo; 0.02% Nb; 0.03% V; 0.015% Cu, all the other content are Fe and inevitable impurity.It is the 300mm strand that continuous casting becomes thickness, finally is rolled into the 42mm Plate Steel.
Press mentioned component, carbon equivalent (CE) is: 0.41%
Molten steel is handled gas content in the steel: [H] 0.8ppm, [O] 27ppm, [N] 50ppm through converter smelting, external refining (LF, VD) simultaneously.
Nonmetallic inclusionsin steel is: category-A＜0.5 grade, category-B＜0.5 grade, 0.5 grade of C class, 0.5 grade of D class.
The nuclear reactor safety shell end socket of present embodiment and cylindrical shell with steel plate after modulation matter is handled; Stretch and the impact property check; The average yield strength of steel plate is that 510MPa, average tensile strength are that 640MPa, shock absorption energy (45 ℃) are controlled at 290-320J, average out to 310J; Steel plate is again after 620 ℃, 10 hours stress-removal of insulation are handled; Its ys and tensile strength slightly descend to some extent; Average yield strength slightly improves at 600MPa, shock absorption energy (45 ℃) at 470MPa, average tensile strength; Basically at 305-350J, average out to 330J satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell fully.
Embodiment four
The nuclear reactor safety shell end socket and the cylindrical shell of present embodiment are used steel, comprise following component by weight percentage: 0.14% C; 0.30% Si; 1.20% Mn; 0.008% P; 0.001% S; 0.44% Ni; 0.15% Cr; 0.15% Mo; 0.015% Nb; 0.05% V; 0.02% Cu, all the other content are Fe and inevitable impurity.It is the 300mm strand that continuous casting becomes thickness, finally is rolled into the 42mm Plate Steel.
Press mentioned component, carbon equivalent (CE) is: 0.44%
Molten steel is handled gas content in the steel: [H] 0.9ppm, [O] 20ppm, [N] 48ppm through converter smelting, external refining (LF, VD) simultaneously.
Nonmetallic inclusionsin steel is: category-A＜0.5 grade, category-B＜0.5 grade, 1.0 grades of C classes, 0.5 grade of D class.
The nuclear reactor safety shell end socket of present embodiment and cylindrical shell with steel plate after modifier treatment; Stretch and the impact property check; The average yield strength of steel plate is that 535MPa, average tensile strength are that 660MPa, shock absorption energy (45 ℃) are controlled at 280-310J, average out to 295J; Steel plate is again after 620 ℃, 10 hours stress-removal of insulation are handled; Its ys and tensile strength slightly descend to some extent; Average yield strength at 500MPa, average tensile strength at 650MPa, shock absorption energy (45 ℃) then basically at 275-305J; About average out to 286J, satisfy the requirement of nuclear reactor safety shell end socket and cylindrical shell fully with steel.
Embodiment five
The nuclear reactor safety shell end socket and the cylindrical shell of present embodiment are used steel, comprise following component by weight percentage: 0.12% C; 0.30% Si; 1.32% Mn; 0.008% P; 0.001% S; 0.44% Ni; 0.16% Cr; 0.10% Mo; 0.015% Nb; 0.05% V; 0.005% Cu, all the other content are Fe and inevitable impurity.It is the 300mm strand that continuous casting becomes thickness, finally is rolled into the 42mm Plate Steel.
Press mentioned component, carbon equivalent (CE) is: 0.43%
Molten steel is handled gas content in the steel: [H] 0.9ppm, [O] 25ppm, [N] 60ppm through converter smelting, external refining (LF, VD) simultaneously.
Nonmetallic inclusionsin steel is: category-A＜0.5 grade, category-B＜0.5 grade, 0.5 grade of C class, 1.0 grades of D classes.
The nuclear reactor safety shell end socket of present embodiment and cylindrical shell with steel plate after modifier treatment; Stretch and the impact property check; The average yield strength of steel plate is that 530MPa, average tensile strength are that 655MPa, shock absorption energy (45 ℃) are controlled at 300-330J, average out to 312J; Steel plate is again after 620 ℃, 10 hours stress-removal of insulation are handled; Its ys and tensile strength slightly descend to some extent; Average yield strength at 505MPa, average tensile strength at 625MPa, shock absorption energy (45 ℃) then basically at 295-335J; Average out to 300J satisfies the requirement with steel of nuclear reactor safety shell end socket and cylindrical shell fully.
Claims (2)
1. nuclear reactor safety shell end socket and cylindrical shell are used steel, it is characterized in that the chemical component weight per-cent of steel is :≤0.20% C; The Si of 0.15%-0.55%; The Mn of 0.90%-1.60%; ≤0.025% P; ≤0.025% S; ≤0.60% Ni; ≤0.30% Cr; ≤0.30% Mo; ≤0.04% Nb; ≤0.07% V; ≤0.35% Cu; Require V+Nb≤0.08% simultaneously, all the other content are Fe and inevitable impurity, and carbon equivalent is 0.40%-0.44% in the steel; Carbon equivalent calculation formula CE=C+Mn/6+ (Cr+Mo+V)/5+ (Ni+Cu)/15, nonmetallic inclusionsin steel A, B, C, D class be mingled with≤and 1.5 grades.
2. a kind of nuclear reactor safety shell end socket according to claim 1 and cylindrical shell are used steel, it is characterized in that the chemical ingredients of steel is: the C of 0.07%-0.14%; The Si of 0.20%-0.40%; The Mn of 1.20%-1.50%; ≤0.012% P; ≤0.003% S; The Ni of 0.35%-0.55%; The Cr of 0.10%-0.20%; The Mo of 0.10%-0.30%; The Nb of 0.01%-0.03%; The V of 0.02%-0.06%; ≤0.10% Cu, H≤1.5ppm, O≤30ppm, N≤60ppm.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010102765029A CN102400058A (en) | 2010-09-07 | 2010-09-07 | Steel for nuclear reactor containment vessel head and cylinder |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2010102765029A CN102400058A (en) | 2010-09-07 | 2010-09-07 | Steel for nuclear reactor containment vessel head and cylinder |
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| CN102400058A true CN102400058A (en) | 2012-04-04 |
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| CN2010102765029A Pending CN102400058A (en) | 2010-09-07 | 2010-09-07 | Steel for nuclear reactor containment vessel head and cylinder |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107365942A (en) * | 2016-05-12 | 2017-11-21 | 鞍钢股份有限公司 | Production method of A36 steel plate for AP1000 nuclear power project |
| CN111270153A (en) * | 2020-03-30 | 2020-06-12 | 南京钢铁股份有限公司 | Steel with thickness of 6mm for nuclear power containment and manufacturing method thereof |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1524976A (en) * | 2003-02-25 | 2004-09-01 | 鞍山钢铁集团公司 | Refractory steel and manufacturing method thereof |
| CN101398165A (en) * | 2008-10-30 | 2009-04-01 | 贵州航天新力铸锻有限责任公司 | Major vapour inlet/outlet joint pipe for nuclear plant steam generator and forging method thereof |
-
2010
- 2010-09-07 CN CN2010102765029A patent/CN102400058A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1524976A (en) * | 2003-02-25 | 2004-09-01 | 鞍山钢铁集团公司 | Refractory steel and manufacturing method thereof |
| CN101398165A (en) * | 2008-10-30 | 2009-04-01 | 贵州航天新力铸锻有限责任公司 | Major vapour inlet/outlet joint pipe for nuclear plant steam generator and forging method thereof |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107365942A (en) * | 2016-05-12 | 2017-11-21 | 鞍钢股份有限公司 | Production method of A36 steel plate for AP1000 nuclear power project |
| CN111270153A (en) * | 2020-03-30 | 2020-06-12 | 南京钢铁股份有限公司 | Steel with thickness of 6mm for nuclear power containment and manufacturing method thereof |
| CN111270153B (en) * | 2020-03-30 | 2022-03-22 | 南京钢铁股份有限公司 | Steel with thickness of 6mm for nuclear power containment and manufacturing method thereof |
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Application publication date: 20120404 |