WO2021093293A1 - 一种核电站安全壳用SA738GrB钢板及制造方法 - Google Patents

一种核电站安全壳用SA738GrB钢板及制造方法 Download PDF

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WO2021093293A1
WO2021093293A1 PCT/CN2020/090750 CN2020090750W WO2021093293A1 WO 2021093293 A1 WO2021093293 A1 WO 2021093293A1 CN 2020090750 W CN2020090750 W CN 2020090750W WO 2021093293 A1 WO2021093293 A1 WO 2021093293A1
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steel plate
nuclear power
sa738grb
temperature
power plant
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PCT/CN2020/090750
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English (en)
French (fr)
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姜在伟
李艳梅
方磊
杨梦奇
于生
张舒展
叶其斌
奚艳红
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南京钢铁股份有限公司
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Priority to GB2208201.0A priority Critical patent/GB2608271A/en
Publication of WO2021093293A1 publication Critical patent/WO2021093293A1/zh

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    • C21C7/00—Treating molten ferrous alloys, e.g. steel, not covered by groups C21C1/00 - C21C5/00
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    • C21D1/00—General methods or devices for heat treatment, e.g. annealing, hardening, quenching or tempering
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    • C21D9/00—Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articles; Furnaces therefor
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    • C22C38/00—Ferrous alloys, e.g. steel alloys
    • C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
    • C22C38/22—Ferrous alloys, e.g. steel alloys containing chromium with molybdenum or tungsten
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    • C22C38/24—Ferrous alloys, e.g. steel alloys containing chromium with vanadium
    • 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
    • C22C38/26—Ferrous alloys, e.g. steel alloys containing chromium with niobium or tantalum
    • C—CHEMISTRY; METALLURGY
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    • C22C38/00—Ferrous alloys, e.g. steel alloys
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    • C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
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    • C—CHEMISTRY; METALLURGY
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    • 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
    • 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
    • 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
    • C22C38/48—Ferrous alloys, e.g. steel alloys containing chromium with nickel with niobium or tantalum
    • 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
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
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    • C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
    • C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
    • C22C38/58—Ferrous alloys, e.g. steel alloys containing chromium with nickel with more than 1.5% by weight of manganese
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/087—Metallic vessels
    • C—CHEMISTRY; METALLURGY
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    • 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
    • C21D2211/00—Microstructure comprising significant phases
    • C21D2211/002—Bainite

Definitions

  • the invention relates to the technical field of steel smelting, in particular to a SA738GrB steel plate for nuclear power plant containment and a manufacturing method.
  • nuclear energy is recognized as a clean, efficient and safe energy source.
  • 2038 90 to 300 1,600 MW reactors will be built globally, and nuclear power development has entered a period of rapid growth.
  • my country's nuclear power construction started in the mid-1980s and has developed rapidly.
  • my country's nuclear power installed capacity in operation and under construction will reach 88 million kilowatts, and nuclear power installed capacity will account for more than 5% of the total domestic power installed capacity.
  • the containment As a protection device for nuclear island equipment, the containment is an important part of the pressurized water reactor nuclear power plant, and it is also the last safety barrier to prevent the leakage of radioactive materials.
  • the main nuclear power reactor type in my country is the AP1000 nuclear power reactor type designed by Westinghouse.
  • the main material used for the steel containment is SA738 Gr.B steel plate.
  • the thickness of the steel type is relatively high, and the technical indicators are demanding, and performance control is difficult. .
  • the performance requirements for their steel containment plates are getting higher and higher. From the perspective of nuclear containment safety, the weld length of the components should be minimized. Therefore, nuclear reactors
  • One of the development directions of the containment is integration and integration. On the basis of ensuring performance, it is very difficult to increase the thickness and width at the same time.
  • Ultra-wide and ultra-thick steel plates have both large thickness and large width at the same time, so they have a higher utilization rate than steel plates of other sizes when making nuclear power plant containment, which not only saves welding workload, but also improves the safety of the containment.
  • none of the invention patents related to this steel type has reached the thickness of 101mm and the width of 4650mm at the same time, such as:
  • CN201811165254.3 discloses a special wide and thick nuclear power conventional island equipment steel and its manufacturing method.
  • the steel contains C: 0.10% ⁇ 0.18%, Si: 0.15% ⁇ 0.40%, Mn: 0.90% ⁇ 1.50%, P ⁇ 0.02%, S ⁇ 0.005%, Ni: 0.10% ⁇ 0.30%, Cr: 0.15% ⁇ 0.30%, V: 0.01% ⁇ 0.05%, Nb: 0.01% ⁇ 0.05%, Als: 0.015% ⁇ 0.04%, balance It is iron and inevitable impurities.
  • the heating temperature of the continuous casting billet is 1200 ⁇ 1250°C, and the furnace time is 4 ⁇ 6h; the opening temperature of the first stage is ⁇ 1100°C, the total reduction rate is ⁇ 60%; the second stage of the opening temperature is 900 ⁇ 950°C, and the final rolling temperature is 800 ⁇ 850°C; normalizing temperature is 880 ⁇ 920°C, holding time is 1 ⁇ 3min/mm, natural cooling after being out of the furnace.
  • the finished steel plate has a thickness of 60-100mm and a width of 4000-5100mm, which meets the use conditions of steel for conventional island equipment in nuclear power plants.
  • the invention patent has reached the highest value in the current industry in terms of width, but its 100mm thick steel plate can only achieve a maximum width of 4200mm, and the strength after normalizing is low.
  • CN201510302071.1 discloses a large-thickness SA738GrA steel plate and its production method, which is composed of the following components by weight percentage: C: 0.14% to 0.16%, Si: 0.25% to 0.45%, Mn: 1.35% to 1.45%, P ⁇ 0.020%, S ⁇ 0.010%, Cr: 0.15% ⁇ 0.20%, Mo ⁇ 0.06%, Ti ⁇ 0.02%, Ni: 0.20% ⁇ 0.30%, Cu ⁇ 0.05%, Al: 0.020% ⁇ 0.050%, V ⁇ 0.07%, Nb ⁇ 0.04%, Nb+V ⁇ 0.07%, the balance is Fe and unavoidable impurities.
  • the steel plate optimizes the composition and ratio of the elements in the steel plate, so that the thickness of the SA738GrA steel plate reaches 112mm, and the obtained steel plate meets the requirements of Class B in the ASME SA578/SA578M flaw detection standard, but the width of the steel plate of the invention is unknown, and the yield strength is only about 310MPa , And the low temperature toughness is poor, and the impact energy at -46°C is about 27 joules.
  • CN201610058164.9 discloses a large thickness SA738GrB steel plate for nuclear island equipment and a production method.
  • the weight percentage of the steel plate composition is: C: 0.05% to 0.20%, Si: 0.15% to 0.55%, Mn: 0.90%% to 1.60%, P ⁇ 0.009%, S ⁇ 0.006%, Cr ⁇ 0.30%, Mo ⁇ 0.30%, Cu ⁇ 0.35%, Ni ⁇ 0.60%, V ⁇ 0.07%, Nb ⁇ 0.04%, Ti ⁇ 0.03%, balance It is Fe and unavoidable impurities.
  • the modified steel plate adopts quenching and tempering heat treatment process, through the formation of composite strengthening of microalloying elements, and obtains a good match of strength and toughness.
  • the thickness of the steel plate can be up to 130mm, but there is also no data on the width.
  • the present invention provides a SA738GrB steel plate for the containment of nuclear power plants.
  • the thickness specification is 101mm and the width specification is 4650mm. Its chemical composition and mass percentage are as follows: C ⁇ 0.2%, Si: 0.13% ⁇ 0.6%, Mn :0.9% ⁇ 1.6%, Ni ⁇ 0.6%, Cr ⁇ 0.3%, Nb ⁇ 0.05%, Mo ⁇ 0.35%, V ⁇ 0.08%, Ti ⁇ 0.03%, the balance is Fe and unavoidable impurities.
  • the finished steel plate designed by the present invention has a thickness of 101mm and a width of 4650mm. It has the advantages of good strength and toughness, weldability, etc., and meets the use requirements of the containment of nuclear power plants.
  • the aforementioned SA738GrB steel plate for nuclear power plant containment has the following chemical composition and mass percentage: C: 0.15%, Mn: 1.53%, P: 0.009%, S: 0.001%, Si: 0.25%, Ni: 0.54% , Cr: 0.022%, Nb: 0.03%, Mo: 0.17%, V: 0.044%, Ti: 0.016%, Alt: 0.04%, the balance is Fe and unavoidable impurities.
  • the aforementioned SA738GrB steel plate for nuclear power plant containment has the following chemical composition and mass percentage: C: 0.14%, Mn: 1.55%, P: 0.008%, S: 0.001%, Si: 0.25%, Ni: 0.55% , Cr: 0.25%, Nb: 0.03%, Mo: 0.28%, V: 0.044%, Ti: 0.017%, Alt: 0.02%, the balance is Fe and unavoidable impurities.
  • the aforementioned SA738GrB steel plate for nuclear power plant containment has the following chemical composition and mass percentage: C: 0.13%, Mn: 1.55%, P: 0.009%, S: 0.001%, Si: 0.25%, Ni: 0.56% , Cr: 0.23%, Nb: 0.03%, Mo: 0.27%, V: 0.045%, Ti: 0.016%, Alt: 0.05%, the balance is Fe and unavoidable impurities.
  • Another object of the present invention is to provide a method for manufacturing SA738GrB steel plate for nuclear power plant containment, which includes the following steps: molten steel pretreatment-converter smelting-refining-continuous casting-heating-rolling-heat treatment, characterized by:
  • Hot metal desulfurization pretreatment starting temperature 1330 ⁇ 1370°C, ending temperature 1320 ⁇ 1350°C, spraying magnesium powder 0.3 ⁇ 1.0kg/ton, lime powder 2.5 ⁇ 4.0kg/ton, ending S ⁇ 0.005%;
  • the molten steel undergoes continuous casting after smelting and refining.
  • the molten steel superheat is 5 ⁇ 25°C
  • the drawing speed is 0.55 ⁇ 0.75m/min
  • the second cooling electromagnetic stirring of continuous casting current 200 ⁇ 450A, frequency 5 ⁇ 7Hz
  • light reduction pressure
  • the lower interval is 50-95%
  • the reduction is 4-8mm
  • the thickness of the continuous casting slab is 320mm;
  • the heating temperature of the continuous casting slab is 1180 ⁇ 1250°C, and the furnace time is 4.8 ⁇ 7.0h.
  • the slab is discharged from the furnace and descaling, it is first cross-rolled to the width of the finished product and then longitudinally rolled.
  • the rolling is divided into two stages: the first stage rolling temperature is 1000 ⁇ 1150°C, the cumulative reduction is 50-70%; in the second stage, the rolling thickness is 184mm, and the cumulative reduction is 40-60%.
  • the steel plate is cooled in the air;
  • the steel plate is heated in the quenching furnace, the heating holding temperature is 890 ⁇ 930°C, and the total holding time is 2.1min/mm; the steel plate is cooled in the roller quenching machine after the heat preservation, and the laminar cooling process includes the high pressure section and In the low pressure section, the laminar flow pressure in the high pressure section is 0.8MPa, the upper and lower water ratio is 0.85, the laminar flow pressure in the low pressure section is 0.5MPa, the upper and lower water ratio is 0.88, and the quenching machine roll gap is set to 101mm; after cooling in the high pressure section, the steel plate Swing for more than 18 minutes in the low pressure section to ensure that the overall temperature of the steel plate after cooling is below 100°C;
  • Tempering The steel plate is heated in the tempering furnace and heated to the tempering temperature of 660 ⁇ 680°C for heat preservation.
  • the total heat preservation time is more than 2.5min/mm. After heat preservation, it is air-cooled out of the furnace.
  • the steel plate of the present invention has a thickness specification of 101mm and a width specification of 4650mm. From the perspective of the safety of the nuclear containment, the weld length of the components can be effectively reduced, and the integration and integration of the containment can be further realized. High utilization rate of steel plate and good safety;
  • the present invention solves the low-temperature impact toughness of nuclear power steel ultra-wide and extra-thick plates.
  • the problem is that the steel plate has good strength and toughness matching.
  • the design of the same chemical composition of the present invention improves the overall performance of the steel plate, and the obtained steel plate has good strength and toughness, especially the low-temperature impact toughness is greatly improved, and the resource consumption of steel plate production is reduced.
  • Fig. 1 is an SEM image of the steel plate obtained in Example 1 of the present invention.
  • the manufacturing method of the above-mentioned steel plate includes the following processes: pretreatment of molten steel-converter smelting-refining-continuous casting-heating-rolling-heat treatment,
  • Hot metal desulfurization pretreatment starting temperature 1330 ⁇ 1370°C, ending temperature 1320 ⁇ 1350°C, spraying magnesium powder 0.3 ⁇ 1.0kg/ton, lime powder 2.5 ⁇ 4.0kg/ton, ending S ⁇ 0.005%;
  • the molten steel undergoes continuous casting after smelting and refining.
  • the molten steel superheat is 5 ⁇ 25°C
  • the drawing speed is 0.55 ⁇ 0.75m/min
  • the second cooling electromagnetic stirring of continuous casting current 200 ⁇ 450A, frequency 5 ⁇ 7Hz
  • light reduction pressure
  • the lower interval is 50-95%
  • the reduction is 4-8mm
  • the thickness of the continuous casting slab is 320mm;
  • the heating temperature of the continuous casting slab is 1180 ⁇ 1250°C, and the furnace time is 4.8 ⁇ 7.0h.
  • the slab is discharged from the furnace and descaling, it is first cross-rolled to the width of the finished product and then longitudinally rolled.
  • the rolling is divided into two stages: the first stage rolling temperature is 1000 ⁇ 1150°C, the cumulative reduction is 50-70%; in the second stage, the rolling thickness is 184mm, and the cumulative reduction is 40-60%.
  • the steel plate is cooled in the air;
  • the steel plate is heated in the quenching furnace, the heating holding temperature is 890 ⁇ 930°C, and the total holding time is 2.1min/mm; the steel plate is cooled in the roller quenching machine after the heat preservation, and the laminar cooling process includes the high pressure section and In the low pressure section, the laminar flow pressure in the high pressure section is 0.8MPa, the upper and lower water ratio is 0.85, the laminar flow pressure in the low pressure section is 0.5MPa, the upper and lower water ratio is 0.88, and the quenching machine roll gap is set to 101mm; after cooling in the high pressure section, the steel plate Swing for more than 18 minutes in the low pressure section to ensure that the overall temperature of the steel plate after cooling is below 100°C;
  • Tempering The steel plate is heated in the tempering furnace and heated to the tempering temperature of 660 ⁇ 680°C for heat preservation.
  • the total heat preservation time is more than 2.5min/mm. After heat preservation, it is air-cooled out of the furnace.
  • Heating and rolling process the heating temperature of the continuous casting slab is 1180 ⁇ 1250°C, and the furnace time is 4.8 ⁇ 7.0h. After the slab is released from the furnace, it will be cross-rolled to the width of the finished product before longitudinal rolling. Rolling is divided into two stages: in the first stage, the opening temperature is 1050°C, and the cumulative reduction is 55%; the second stage has a thickness of 184mm and the cumulative reduction is 45%. After rolling, the steel plate is cooled in the air.
  • Samples were taken from the steel plates of the examples and simulated post-weld heat treatment experiments were carried out. The process was as follows: holding temperature 620 ⁇ 10°C, holding time 10h, loading furnace temperature ⁇ 425°C, temperature rise and fall rate above 425°C 56°C/h.
  • the thickness of the steel plate is 1/4 to obtain a uniform tempered bainite structure.
  • the steel plate designed in the present invention has a thickness specification of 101mm and a width specification of 4650mm. From the perspective of the safety of the nuclear containment, the weld length of the components can be effectively reduced, and the integration and integration of the containment can be further realized.
  • the use of steel plates The rate is high and the safety is better.
  • the design of the same chemical composition improves the overall performance of the steel plate, and the resulting steel plate has good strength and toughness, especially the low-temperature impact toughness is greatly improved, which reduces the resource consumption of steel plate production.

Abstract

一种核电站安全壳用SA738GrB钢板，涉及钢铁冶炼技术领域，厚度规格为101mm，宽度规格为4650mm，其化学成分及质量百分比如下：C≤0.2％，Si：0.13％～0.6％，Mn：0.9％～1.6％，Ni≤0.6％，Cr≤0.3％，Nb≤0.05％，Mo≤0.35％，V≤0.08％，Ti≤0.03％，余量为Fe和不可避免的杂质。成品厚度在101mm，同时宽度达到4650mm，具有良好的强韧性、可焊接性等优点，满足核电站安全壳的使用要求。

Description

一种核电站安全壳用SA738GrB钢板及制造方法 技术领域
本发明涉及钢铁冶炼技术领域，特别是涉及一种核电站安全壳用SA738GrB钢板及制造方法。
背景技术
目前，核能被公认为是一种清洁、高效和安全的能源。据国际权威机构预测，到2038年，全球将兴建90座至300座1600兆瓦的反应堆，核电发展进入快速上升期。我国核电建设起步于上世纪八十年代中期，发展迅猛，截止到2017年，大陆地区在运核电机组共37台，在建核电机组共19台，在建核电机组数量居世界第一。到2020年，我国核电运行和在建装机将达到8800万千瓦，核电装机容量占国内电力总装机容量5％以上。
安全壳作为核岛设备的保护装置，是压水堆核电站的重要组成部分，也是防止放射性物质泄漏的最后一道安全屏障。目前，我国的主要核电堆型是西屋公司设计的AP1000核电堆型，其钢质安全壳主要用料是SA738 Gr.B钢板，钢种厚度规格较高，并且技术指标要求苛刻，性能控制较为困难。随着国际上对于核电站安全性要求的提高，对于其钢制安全壳钢板的性能要求也越来越高，从核安全壳安全性的角度考虑，应尽量减少组件的焊缝长度，因此，核反应堆安全壳的发展方向之一就是一体化和整体化，在保证性能的基础上，同时提高厚度和宽度，具有很大的难度。
超宽超厚钢板由于同时兼具大厚度和大宽度，在制作核电站安全壳时比其他尺寸的钢板利用率更高，不仅能节省焊接工作量，而且能提高安全壳的安全性。目前，关于该钢种的发明专利中，均未能同时达到101mm厚，4650mm宽，如：
CN201811165254.3公开一种特宽特厚核电常规岛设备用钢及其制造方法，钢中含有C：0.10％～0.18％，Si：0.15％～0.40％，Mn：0.90％～1.50％，P≤0.02％， S≤0.005％，Ni：0.10％～0.30％，Cr：0.15％～0.30％，V：0.01％～0.05％，Nb：0.01％～0.05％，Als：0.015％～0.04％，余量为铁和不可避免的杂质。连铸坯加热温度1200～1250℃，在炉时间4～6h；第Ⅰ阶段开轧温度≥1100℃，总压下率≥60％；第Ⅱ阶段开轧温度900～950℃，终轧温度800～850℃；正火温度880～920℃，保温时间1～3min/mm，出炉后自然冷却。成品钢板厚60～100mm，宽4000～5100mm，满足核电站常规岛设备用钢的使用条件。该发明专利在宽度方面达到了目前行业的最高值，但其100mm厚的钢板宽度最大只能做到4200mm，且正火后强度较低。
CN201510302071.1公开了一种大厚度SA738GrA钢板及其生产方法，其由以下重量百分比的成分组成：C：0.14％～0.16％，Si：0.25％～0.45％，Mn：1.35％～1.45％，P≤0.020％，S≤0.010％，Cr：0.15％～0.20％，Mo≤0.06％，Ti≤0.02％，Ni：0.20％～0.30％，Cu≤0.05％，Al：0.020％～0.050％，V≤0.07％，Nb≤0.04％，Nb+V≤0.07％，余量为Fe和不可避免的杂质。该钢板优化了钢板中各元素组分及配比，使得SA738GrA钢板的厚度达到112mm，所得钢板满足ASME SA578/SA578M探伤标准中B级的要求，但是该发明钢板宽度未知，屈服强度仅在310MPa左右，且低温韧性较差，-46℃冲击功约27焦耳左右。
CN201610058164.9公开了一种核岛设备用大厚度SA738GrB钢板及生产方法，钢板成分的重量百分含量为：C：0.05％～0.20％，Si：0.15％～0.55％，Mn：0.90％％～1.60％，P≤0.009％，S≤0.006％，Cr≤0.30％，Mo≤0.30％，Cu≤0.35％，Ni≤0.60％，V≤0.07％，Nb≤0.04％，Ti≤0.03％，余量为Fe和不可避免的杂质。改钢板采用调质热处理工艺，通过微合金元素形成复合强化，获得了良好的强韧性匹配。该钢板厚度最厚可达130mm，但同样对于宽度无数据。
发明内容
为了解决以上技术问题，本发明提供一种核电站安全壳用SA738GrB钢板，厚度规格为101mm，宽度规格为4650mm，其化学成分及质量百分比如下：C≤0.2％， Si：0.13％～0.6％，Mn：0.9％～1.6％，Ni≤0.6％，Cr≤0.3％，Nb≤0.05％，Mo≤0.35％，V≤0.08％，Ti≤0.03％，余量为Fe和不可避免的杂质。
技术效果：本发明设计的钢板成品厚度在101mm，同时宽度达到4650mm，具有良好的强韧性、可焊接性等优点，满足核电站安全壳的使用要求。
本发明进一步限定的技术方案是：
前所述的一种核电站安全壳用SA738GrB钢板，其化学成分及质量百分比如下：C：0.15％，Mn：1.53％，P：0.009％，S：0.001％，Si：0.25％，Ni：0.54％，Cr：0.022％，Nb：0.03％，Mo：0.17％，V：0.044％，Ti：0.016％，Alt：0.04％，余量为Fe和不可避免的杂质。
前所述的一种核电站安全壳用SA738GrB钢板，其化学成分及质量百分比如下：C：0.14％，Mn：1.55％，P：0.008％，S：0.001％，Si：0.25％，Ni：0.55％，Cr：0.25％，Nb：0.03％，Mo：0.28％，V：0.044％，Ti：0.017％，Alt：0.02％，余量为Fe和不可避免的杂质。
前所述的一种核电站安全壳用SA738GrB钢板，其化学成分及质量百分比如下：C：0.13％，Mn：1.55％，P：0.009％，S：0.001％，Si：0.25％，Ni：0.56％，Cr：0.23％，Nb：0.03％，Mo：0.27％，V：0.045％，Ti：0.016％，Alt：0.05％，余量为Fe和不可避免的杂质。
本发明的另一目的在于提供一种核电站安全壳用SA738GrB钢板的制造方法，包括以下工序：钢水预处理-转炉冶炼-精炼-连铸-加热-轧制-热处理，其特征在于：
铁水脱硫预处理：开始温度1330～1370℃，结束温度1320～1350℃，喷入镁粉0.3～1.0kg/吨、石灰粉2.5～4.0kg/吨，结束S≤0.005％；
钢水经过冶炼和精炼后进行连铸，钢水过热度5～25℃，拉坯速度0.55～0.75m/min，连铸二冷电磁搅拌：电流200～450A、频率5～7Hz，轻压下：压下 区间50～95％、压下量4～8mm，连铸坯厚度为320mm；
连铸坯加热温度1180～1250℃，在炉时间4.8～7.0h，钢坯出炉除鳞后，先横轧至成品宽度再进行纵轧，分两阶段轧制：第一阶段轧制温度为1000～1150℃，累计压下量50～70％；第二阶段开轧厚度184mm，累计压下量40～60％，轧后钢板在空气中冷却；
淬火：钢板在淬火炉进行加热，加热的保温温度为890～930℃，总保温时间为2.1min/mm；钢板在保温后在辊式淬火机进行层流冷却，层流冷却过程包括高压段和低压段，高压段层流压力为0.8MPa，上下水比为0.85，低压段层流压力为0.5MPa，上下水比为0.88，淬火机轧辊辊缝设定为101mm；在高压段冷却后，钢板在低压段进行摇摆时间18min以上，保证钢板冷却后的整体温度在100℃以下；
回火：钢板进回火炉进行加热，加热至回火温度660～680℃进行保温，总保温时间2.5min/mm以上，保温后出炉空冷。
本发明的有益效果是：
(1)本发明的钢板在厚度规格达到101mm的同时，宽度规格达到4650mm，从核安全壳安全性的角度考虑，可有效减少组件的焊缝长度，进一步实现安全壳的一体化和整体化，钢板利用率高，安全性较好；
(2)本发明通过采用高洁净冶炼与低偏析连铸、两阶段控制轧制及离线辊式高强度高均匀性淬火和回火热处理，解决了核电钢超宽特厚板的低温冲击韧性较低的问题，钢板具有良好的强韧性匹配，经检测本发明方法所得钢板交货状态厚向1/4处的力学性能：R P0.2≥635MPa，R m≥710MPa，A 5d≥20％，-25℃K v8(平均值)≥84J，-35℃K v8(平均值)≥52J；模拟焊后热处理的性能：R p0.2≥615MPa，R m≥710MPa，A 5d≥21％，-35℃横向K V8冲击功平均值≥75J；
(3)本发明与普通控轧及热处理钢板相比，同等化学成分设计提高了钢板 的综合性能，所得钢板强韧性良好，尤其是低温冲击韧性大幅提升，降低了钢板生产资源消耗。
附图说明
图1为本发明中实施例1所得钢板的SEM图像。
具体实施方式
一种核电站安全壳用SA738GrB钢板，厚度规格为101mm，宽度规格为4650mm，其化学成分及质量百分比如下：C≤0.2％，Si：0.13％～0.6％，Mn：0.9％～1.6％，Ni≤0.6％，Cr≤0.3％，Nb≤0.05％，Mo≤0.35％，V≤0.08％，Ti≤0.03％，余量为Fe和不可避免的杂质。
上述钢板的制造方法，包括以下工序：钢水预处理-转炉冶炼-精炼-连铸-加热-轧制-热处理，
铁水脱硫预处理：开始温度1330～1370℃，结束温度1320～1350℃，喷入镁粉0.3～1.0kg/吨、石灰粉2.5～4.0kg/吨，结束S≤0.005％；
钢水经过冶炼和精炼后进行连铸，钢水过热度5～25℃，拉坯速度0.55～0.75m/min，连铸二冷电磁搅拌：电流200～450A、频率5～7Hz，轻压下：压下区间50～95％、压下量4～8mm，连铸坯厚度为320mm；
连铸坯加热温度1180～1250℃，在炉时间4.8～7.0h，钢坯出炉除鳞后，先横轧至成品宽度再进行纵轧，分两阶段轧制：第一阶段轧制温度为1000～1150℃，累计压下量50～70％；第二阶段开轧厚度184mm，累计压下量40～60％，轧后钢板在空气中冷却；
淬火：钢板在淬火炉进行加热，加热的保温温度为890～930℃，总保温时间为2.1min/mm；钢板在保温后在辊式淬火机进行层流冷却，层流冷却过程包括高压段和低压段，高压段层流压力为0.8MPa，上下水比为0.85，低压段层流压力为0.5MPa，上下水比为0.88，淬火机轧辊辊缝设定为101mm；在高压段冷却 后，钢板在低压段进行摇摆时间18min以上，保证钢板冷却后的整体温度在100℃以下；
回火：钢板进回火炉进行加热，加热至回火温度660～680℃进行保温，总保温时间2.5min/mm以上，保温后出炉空冷。
下面结合实施例1-实施例3对本发明的技术方案作进一步说明。
表1各实施例钢冶炼化学成分(wt，％)
Figure PCTCN2020090750-appb-000001
加热轧制工序：连铸坯加热温度1180～1250℃，在炉时间4.8～7.0h，钢坯出炉除鳞后，先横轧至成品宽度再进行纵轧。分两阶段轧制：第一阶段开轧温度为1050℃，累计压下量55％；第二阶段开轧厚度184mm，累计压下量45％。轧后钢板在空气中冷却。
表2各实施例钢的热处理工艺
Figure PCTCN2020090750-appb-000002
表3各实施例钢的回火态力学性能
Figure PCTCN2020090750-appb-000003
从实施例钢板取样，进行模拟焊后热处理实验，工艺为：保温温度620±10℃，保温时间10h，装出炉温度≤425℃，425℃以上升降温速率56℃/h。
表4各实施例钢模拟焊后热处理的力学性能
Figure PCTCN2020090750-appb-000004
如图1，钢板厚向1/4处获得均匀的回火贝氏体组织。本发明设计的钢板在厚度规格达到101mm的同时，宽度规格达到4650mm，从核安全壳安全性的角度考虑，可有效减少组件的焊缝长度，进一步实现安全壳的一体化和整体化，钢板利用率高，安全性较好。与普通控轧及热处理钢板相比，同等化学成分设计提高了钢板的综合性能，所得钢板强韧性良好，尤其是低温冲击韧性大幅提升，降低了钢板生产资源消耗。
除上述实施例外，本发明还可以有其他实施方式。凡采用等同替换或等效变换形成的技术方案，均落在本发明要求的保护范围。

Claims (5)

  1. 一种核电站安全壳用SA738GrB钢板，其特征在于：厚度规格为101mm，宽度规格为4650mm，其化学成分及质量百分比如下：C≤0.2％，Si：0.13％～0.6％，Mn：0.9％～1.6％，Ni≤0.6％，Cr≤0.3％，Nb≤0.05％，Mo≤0.35％，V≤0.08％，Ti≤0.03％，余量为Fe和不可避免的杂质。
  2. 根据权利要求1所述的一种核电站安全壳用SA738GrB钢板，其特征在于，其化学成分及质量百分比如下：C：0.15％，Mn：1.53％，P：0.009％，S：0.001％，Si：0.25％，Ni：0.54％，Cr：0.022％，Nb：0.03％，Mo：0.17％，V：0.044％，Ti：0.016％，Alt：0.04％，余量为Fe和不可避免的杂质。
  3. 根据权利要求1所述的一种核电站安全壳用SA738GrB钢板，其特征在于，其化学成分及质量百分比如下：C：0.14％，Mn：1.55％，P：0.008％，S：0.001％，Si：0.25％，Ni：0.55％，Cr：0.25％，Nb：0.03％，Mo：0.28％，V：0.044％，Ti：0.017％，Alt：0.02％，余量为Fe和不可避免的杂质。
  4. 根据权利要求1所述的一种核电站安全壳用SA738GrB钢板，其特征在于，其化学成分及质量百分比如下：C：0.13％，Mn：1.55％，P：0.009％，S：0.001％，Si：0.25％，Ni：0.56％，Cr：0.23％，Nb：0.03％，Mo：0.27％，V：0.045％，Ti：0.016％，Alt：0.05％，余量为Fe和不可避免的杂质。
  5. 应用于权利要求1所述的一种核电站安全壳用SA738GrB钢板的制造方法，包括以下工序：钢水预处理-转炉冶炼-精炼-连铸-加热-轧制-热处理，其特征在于：
    铁水脱硫预处理：开始温度1330～1370℃，结束温度1320～1350℃，喷入镁粉0.3～1.0kg/吨、石灰粉2.5～4.0kg/吨，结束S≤0.005％；
    钢水经过冶炼和精炼后进行连铸，钢水过热度5～25℃，拉坯速度0.55～0.75m/min，连铸二冷电磁搅拌：电流200～450A、频率5～7Hz，轻压下：压下区间50～95％、压下量4～8mm，连铸坯厚度为320mm；
    连铸坯加热温度1180～1250℃，在炉时间4.8～7.0h，钢坯出炉除鳞后， 先横轧至成品宽度再进行纵轧，分两阶段轧制：第一阶段轧制温度为1000～1150℃，累计压下量50～70％；第二阶段开轧厚度184mm，累计压下量40～60％，轧后钢板在空气中冷却；
    淬火：钢板在淬火炉进行加热，加热的保温温度为890～930℃，总保温时间为2.1min/mm；钢板在保温后在辊式淬火机进行层流冷却，层流冷却过程包括高压段和低压段，高压段层流压力为0.8MPa，上下水比为0.85，低压段层流压力为0.5MPa，上下水比为0.88，淬火机轧辊辊缝设定为101mm；在高压段冷却后，钢板在低压段进行摇摆时间18min以上，保证钢板冷却后的整体温度在100℃以下；
    回火：钢板进回火炉进行加热，加热至回火温度660～680℃进行保温，总保温时间2.5min/mm以上，保温后出炉空冷。
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