CN102808074B - Casting blank heat treatment method of stainless steel welding strip for nuclear power - Google Patents
Casting blank heat treatment method of stainless steel welding strip for nuclear power Download PDFInfo
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- CN102808074B CN102808074B CN 201210290088 CN201210290088A CN102808074B CN 102808074 B CN102808074 B CN 102808074B CN 201210290088 CN201210290088 CN 201210290088 CN 201210290088 A CN201210290088 A CN 201210290088A CN 102808074 B CN102808074 B CN 102808074B
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Abstract
The invention provides a casting blank heat treatment method of a stainless steel welding strip for nuclear power. The casting blank heat treatment method of the stainless steel welding strip for the nuclear power includes the steps: polishing the surface of a continuous casting blank prior to performing hot delivery of the continuous casting blank to a trolley type high-temperature annealing furnace; heating the continuous casting blank to an expected temperature in the high-temperature annealing furnace; holding the continuous casting blank at the expected temperature; cooling the continuous casting blank in air after completion of temperature holding; and conveying the air-cooled continuous casting blank to a walking-beam heating furnace and performing hot-rolling forming after soaking. The continuous casting blank subjected to heat treatment is good in high-temperature thermoplasticity at a hot rolling stage, and hot-rolling edge crack of the casting blank of the stainless steel welding strip for the nuclear power can be eliminated, so that the casting blank can go through hot-rolling forming smoothly, and domestication of stainless steel welding strips for the nuclear power is achieved.
Description
Technical field
The present invention relates to the strand heat treating method that a kind of effective control welding splits with stainless steel hot edging, particularly a kind ofly control the strand heat treating method that nuclear power splits with stainless steel surfacing strip hot rolling limit.
Background technology
Along with the development of nuclear power energy industry, the austenitic stainless steel built-up welding is on nuclear power plant equipment
Be widely used, as reactor pressure vessel cylindrical shell overlay cladding, potentiostat cylindrical shell overlay cladding, steam generator sheetpile layer etc.It has satisfied the requirement of the anti-refrigerant corrosion of equipment unit in the equipment of assurance mechanical property.
Welding has higher plasticity and toughness, corrosion resistance nature and processing characteristics preferably with austenitic stainless steel.In actual product, owing to be subjected to effect and the not high enough influence of austenite phase forming element (as Ni) content of ferritic phase stabilizing element (as Cr), in the austenite stainless structure of steel, still can there be the ferritic phase of some amount.
Ferritic phase is on good terms than austenite and is dissolved more detrimental impurity (as S, P etc.), can prevent these element segregations, reduces the formation of low melting point eutectic compound; Can also the refinement column crystal, crystal boundary is increased, the low melting point eutectic compound is therefore divided and be dispersed in discontinuously on each crystal boundary, thereby has reduced welding hot crack tendency.Therefore, the austenitic stainless steel welding that is applied to the nuclear power generating equipment built-up welding requires ferritic content between 13%～15%, to prevent the generation of HOT CRACK FOR WELDING P, guarantees the quality product of weld seam.
Because nuclear power reaches about 15% with ferrite content in the stainless steel surfacing strip, cause existing in its strand a large amount of ferrite network tissues, the appearance of these reticulattions greatly reduces the high temperature of austenitic stainless steel in course of hot rolling and prolongs plasticity, increased the proneness of austenitic stainless steel thermogenesis processing crackle, make such stainless steel in hot rolling roughing process, serious limit will take place and split phenomenon, can't pass through hot-roll forming.
Summary of the invention
Split phenomenon in order to eliminate nuclear power with stainless steel surfacing strip strand hot rolling limit, the invention provides a kind of nuclear power stainless steel surfacing strip strand heat treating method, one of its purpose is the form that changes ferrite network in the strand, makes this connective tissue become the small sized particles shape of dispersion; Two of purpose is that strand serious limit can not occur and splits phenomenon in course of hot rolling, can pass through hot-roll forming smoothly.
In order to achieve the above object, the technical solution used in the present invention is: nuclear power of the present invention includes following chemical ingredients with stainless steel surfacing strip, mass percent is: C :≤0.02%, Si:0.20%～0.60%, Mn:1.70%～2.20%, P: S≤0.02% :≤0.01%, Cr:23.50%～24.50%, Ni:13.00%～13.50%, Cu: N≤0.1% :≤0.04%, and this heat treating method may further comprise the steps:
1. the red pallet car type high-temperature annealing furnace of delivering to after the continuously cast bloom figuring of surface;
2. in high-temperature annealing furnace, continuously cast bloom is heated to preferred temperature, temperature range between 1100 ℃～1200 ℃, 50～100 ℃/h of rate of heating;
3. 2. continuously cast bloom is incubated under the described temperature in step, soaking time 60～240 minutes;
4. after 3. step is finished, in air, continuously cast bloom is naturally cooled to room temperature;
5. the continuously cast bloom behind the air cooling is delivered in the walking beam furnace, hot-roll forming after the soaking;
Behind above-mentioned strand heat treatment step, continuously cast bloom shows good high-temperature thermoplasticity,
Serious limit when high temperature rolling, no longer occurs and split phenomenon, can pass through hot-roll forming smoothly.
Comparison diagram 1 and Fig. 2 as can be seen, adopt strand thermal treatment of the present invention after, in the high temperature microstructure during the continuously cast bloom hot rolling, the ferrite pattern disperses independently small sized particles shape by netted the changing into of original big area bar.Plain weak austenite and the difference of ferrite on two phase structure and performance changed of this granular iron, reduced the additional stress that produces on the two-phase interface, after this also passes through strand thermal treatment of the present invention just, the hot rolling limit of continuously cast bloom is split and is effectively controlled, can be smoothly reason by hot-roll forming.
Description of drawings
High temperature microstructure metallograph (photo) when Fig. 1 is the continuously cast bloom hot rolling of adopting after the present invention heats.
The high temperature microstructure metallograph (photo) of continuously cast bloom when Fig. 2 heats the back hot rolling for adopting conventional heat treating method.
Embodiment
Further the strand heat treating method of nuclear power of the present invention with stainless steel surfacing strip described in detail below in conjunction with embodiment.
Embodiment: present embodiment is for effectively controlling the strand heat treating method that nuclear power splits with stainless steel surfacing strip hot rolling limit, and this method includes following steps:
1. the red pallet car type high-temperature annealing furnace of delivering to after the continuously cast bloom figuring of surface;
2. in high-temperature annealing furnace, continuously cast bloom is heated to preferred temperature, temperature range between 1100 ℃～1200 ℃, 50～100 ℃/h of rate of heating;
3. 2. continuously cast bloom is being incubated under the described preferred temperature, soaking time 60～240 minutes;
4. after 3. step is finished, in air, continuously cast bloom is cooled to room temperature;
5. the continuously cast bloom behind the air cooling is delivered in the walking beam furnace, hot-roll forming after the soaking;
6. behind above-mentioned strand heat treatment step, continuously cast bloom shows good high-temperature thermoplasticity, serious limit no longer occurs and split phenomenon when high temperature rolling, can pass through hot-roll forming smoothly.
Nuclear power of the present invention includes following chemical ingredients with stainless steel surfacing strip, and mass percent is: C :≤0.02%; Si:0.20%～0.60%; Mn:1.70%～2.20%; P :≤0.02%; S :≤0.01%; Cr:23.50%～24.50%; Ni:13.00%～13.50%; Cu :≤0.1%; N :≤0.04%.
Claims (1)
1. a nuclear power comprises the steps: with stainless steel surfacing strip strand heat treating method
1. the red pallet car type high-temperature annealing furnace of delivering to after the continuously cast bloom figuring of surface;
2. in high-temperature annealing furnace, continuously cast bloom is heated to preferred temperature, described preferred temperature scope between 1100 ℃～1200 ℃, 50～100 ℃/h of rate of heating;
3. 2. continuously cast bloom is being incubated under the described preferred temperature, soaking time 60～120 minutes;
4. after 3. step is finished, in air, continuously cast bloom is cooled to room temperature;
5. the continuously cast bloom behind the air cooling is delivered in the walking beam furnace, hot-roll forming after the soaking; It is characterized in that described nuclear power with the mass percent that stainless steel surfacing strip includes following chemical ingredients is: C :≤0.02%; Si:0.20%～0.60%; Mn:1.70%～2.20%; P :≤0.02%; S :≤0.01%; Cr:23.50%～24.50%; Ni:13.00%～13.50%; Cu :≤0.1%; N :≤0.04%.
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| CN102808074B true CN102808074B (en) | 2013-09-25 |
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| CN105080968B (en) * | 2015-05-19 | 2017-10-27 | 浙江青山钢铁有限公司 | A kind of continuous casting billet milling method of super-duplex stainless steel |
| CN107779787B (en) * | 2016-08-30 | 2020-07-14 | 浙江大隆合金钢有限公司 | Austenitic stainless steel for Z2CN19-10NS nuclear power pipeline and steel ingot production method |
| CN112974562B (en) * | 2021-03-31 | 2023-04-07 | 甘肃酒钢集团宏兴钢铁股份有限公司 | Production method of stainless steel hot-rolled coil for welding strip |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102605284A (en) * | 2011-01-25 | 2012-07-25 | 宝山钢铁股份有限公司 | Duplex stainless steel and manufacturing method thereof |
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| JP3409965B2 (en) * | 1996-05-22 | 2003-05-26 | 川崎製鉄株式会社 | Austenitic stainless hot-rolled steel sheet excellent in deep drawability and method for producing the same |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN102605284A (en) * | 2011-01-25 | 2012-07-25 | 宝山钢铁股份有限公司 | Duplex stainless steel and manufacturing method thereof |
Non-Patent Citations (4)
| Title |
|---|
| 刘尚潭等.新型水电站用马氏体不锈钢钢板的研制.《世界钢铁》.2011,(第6期),第23页1 水电钢板的工艺技术设计. |
| 刘洪涛等.连铸3Cr12不锈钢中板工艺性能研究.《铸造设备研究》.2007,(第2期),第17-18页2工艺分析. |
| 新型水电站用马氏体不锈钢钢板的研制;刘尚潭等;《世界钢铁》;20110630(第6期);第23页1 水电钢板的工艺技术设计 * |
| 连铸3Cr12不锈钢中板工艺性能研究;刘洪涛等;《铸造设备研究》;20070430(第2期);第17-18页2工艺分析 * |
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