CN103361567B - A kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof - Google Patents

A kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof Download PDF

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CN103361567B
CN103361567B CN201210092194.3A CN201210092194A CN103361567B CN 103361567 B CN103361567 B CN 103361567B CN 201210092194 A CN201210092194 A CN 201210092194A CN 103361567 B CN103361567 B CN 103361567B
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steel
temperature
rolling
potentiostat
nuclear power
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CN201210092194.3A
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Chinese (zh)
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CN103361567A (en
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孙殿东
王勇
张起生
王长顺
苏春霞
乔馨
陈本文
王动
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鞍钢股份有限公司
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Abstract

The invention provides a kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof, the component of steel: C 0.10%-0.25%, Si 0.15%-0.35%, Mn 0.80%-0.95%, P ≤ 0.010%, S ≤ 0.010%, Ni 0.50%-0.80%, Cr 0.20%-0.60%, Al 0.005%-0.040%, Mo 0.40%-0.70%, V 0.005%-0.01%, Ti 0.005%-0.01%, Cu ≤ 0.10%, remaining is Fe.Method comprises 1) smelt: & lt; The steel plate of 70mm adopts converter, continuous casting working procedure; The steel plate of >=70mm adopts molding operations; 2) rolling: for continuously cast bloom billet heating temperature 1150 ~ 1250 DEG C, finishing temperature >=1000 DEG C, recrystallization zone, Unhydrated cement rolling temperature 830 ~ 880 DEG C, total reduction is greater than 70%; Static ingot heats at batch-type furnace, Heating temperature >=1200 DEG C, start rolling temperature >=1050 DEG C; 3) modifier treatment: quenching temperature 850 ~ 930 DEG C, soaking time 2-4min/mm; Tempering temperature 630 ~ 680 DEG C, soaking time 4-10min/mm.Product of the present invention can meet indices requirement.<!--1-->

Description

A kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof
Technical field
The invention belongs to ferrous material technical field, particularly pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof.
Background technology
Nearly half a century has been gone through in the application of nuclear power, fact proved, the application of nuclear power, except energy Optimization of Energy Structure, is created outside huge economic benefit, even more important effect is to reduce fossil oil for the pollution of environment, meets the Major Strategic requirement of China's Sustainable development.In view of nuclear power is a kind of safety, clean, economic, the reliable energy, many developed countries and some developing countries and regions, be placed on nuclear power the status of first developing.Nuclear power technology has also developed into EPR and AP1000 for representing Generation Ⅲ, and the research-and-development activity carrying out Generation Ⅳ has been set about by world nuclear application power.
In the compacted clay liners built with EPR and AP1000 Generation Ⅲ, potentiostat steel plays the vital role maintaining pressure-stabilisation in nuclear power generating sets primary Ioops system operation.Special in having an accident, preventing system overpressure, by pressure-controlling in allowed limits, is the important leverage of nuclear plant safety.
That EPR and AP1000 third generation pressurized-water reactor nuclear power plant potentiostat steel mainly adopts is ASMESA508Gr.3 or RCC-M16MND5.The former is alloy steel forging, and tensile strength mostly controls between 550-650Mpa, and 4.4 DEG C of shock absorption energy hole are at 41-200J; The latter is manganese nickel Low Alloy Steel Plate, and tensile strength mostly controls at 550-670Mpa, and-20 DEG C of shock absorption energy hole are at 40-240J.But because potentiostat steel is as a kind of pressurized-water reactor nuclear power plant nuclear island primary device steel, under the normal temperature tensile strength after long-time Simulated post-weld heat treatment and condition of delivery, high temperature tensile strength has decline to a certain degree especially, is difficult to the demand meeting third generation EPR and AP1000 pressurized-water reactor nuclear power plant potentiostat steel.As thickness be the 16MND5 steel plate of 50mm after modifier treatment, yield strength (Rel) and tensile strength (Rm) are respectively 535N/mm 2and 630N/mm 2(index request Rel>=485N/mm 2, Rm>=620-795N/mm 2).From performance index, steel plate is after modifier treatment, and intensity meets index request completely, but tensile strength surplus is little.But after Simulated post-weld heat treatment, steel plate yield strength and tensile strength all will decline 20-30N/mm 2, illustrate that its tensile strength can not meet index request; 350 DEG C time, the yield strength of steel plate and tensile strength decline obviously, can not meet the demand that pressurized-water reactor nuclear island primary device is built.
Based on above reason, necessary by optimizing chemical composition and formulating rational production technique, produce a kind of potentiostat steel of high-intensity high-tenacity, meet the requirement of EPR and AP1000 third generation pressurized-water reactor nuclear power plant potentiostat safe operation.
Summary of the invention
The object of the invention is to the deficiency overcoming the existence of above-mentioned prior art, a kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof are provided, state steel plate of not only delivering goods has good toughness and strength matching, the requirement of technical indicator can be met, and the mechanical property of steel plate of Simulated post-weld heat treatment state and 350 DEG C of conditions of high temperature all can keep higher level, meet the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.
The present invention is achieved in that the components based on weight percentage of this pressurized-water reactor nuclear power plant potentiostat steel: C0.10%-0.25%, Si0.15%-0.35%, Mn0.80%-0.95%, P≤0.010%, S≤0.010%, Ni0.50%-0.80%, Cr0.20%-0.60%, Al0.005%-0.040%, Mo0.40%-0.70%, V0.005%-0.01%, Ti0.005%-0.01%, Cu≤0.10%, and surplus is Fe and inevitable impurity.
The reason that the present invention adopts mentioned component to design is as follows:
(1) C: along with the rising of C content in steel, the hardness of steel and intensity increase, and toughness and plasticity reduce, and can improve radiation embrittlement tendency simultaneously.For making steel plate through long-time Simulated post-weld heat treatment and under 350 DEG C of high temperature, intensity and toughness reach good coupling, and therefore in application claims steel, C content should within the scope of control 0.15-0.25%.
(2) Si:Si can significantly improve tensile strength, improves yield strength by a small margin, but the plasticity of Si too high levels infringement steel plate and toughness, for ensureing the over-all properties of steel plate, Si content is controlled be 0.15-0.35%.
(3) Mn: in steel, Mn element is generally beneficial element, effectively can improve the hardening capacity of steel, improve yield-point, because Mn is for expanding γ phase block elements, under thermal spike effect, lattice distortion is increased, irradiation effect is comparatively large, therefore requires that in steel, Mn content controls in OK range, namely controls within the scope of 0.80-0.95%.
(4) Ni:Ni can improve intensity and hardening capacity, and improves low-temperature performance by fining ferrite grains, makes steel plate also can have higher toughness while having sufficient intensity, and therefore in application claims steel, Ni content controls as 0.50-0.80%.
(5) Cr: in steel, Cr element is for reducing austenite phase field element, can improve hardening capacity, solidity to corrosion and oxidation-resistance, reduces the trend of radiation embrittlement.Especially the intensity of steel under high temperature can be improved, to ensureing that the high-temperature behavior of steel is particularly important.Therefore in application claims steel, Cr content controls as 0.20-0.60%.
(6) Al:Al is the effective element of adjustment crystalline grain of steel degree, is combined and forms dystectic small-particle, have the effect of crystal grain thinning with appropriate N.
(7) Mo:Mo is as main alloy element, and its effect is intensity, plasticity, hardening capacity, the raising thermotolerance of increase steel and eliminates temper brittleness, and Mo can reduce γ phase region, has the trend reducing radiation embrittlement.
(8) V, Ti: fine grained steel is less than coarse-grained steel irradiation fragility.Add V, Ti is by solution strengthening with the effect of pinning dislocation and crystal grain thinning, and can improve normal temperature and the hot strength of steel, the scope therefore adding V, Ti in steel is 0.005-0.01%.
(9) Cu:Cu is the element the most harmful to radiation embrittlement, therefore usually requires that the Cu content in midium-carbon steel should lower than 0.10%.
(10) P:P is a kind of harmful element, causing the fragility of steel to aggravate, also making yield-point and yield tensile ratio significantly improve, plasticity and toughness deteriorate, to being welded with disadvantageous effect.Irradiation test shows simultaneously, and P is also very responsive to radiation embrittlement, and therefore require that the P content in steel is more low better, application claims is lower than 0.010%.
(11) S:S austenite grain boundary place in steel forms FeS and MnS sulfide, and can reduce impelling strength and the welding property of steel, S also has the tendency accelerating radiation embrittlement simultaneously.Therefore require that in steel, S content should be limited in less than 0.010%.
(12) gas H, O, N: H, O, N excessive in steel produce adverse influence to the performance of steel, also can increase radiation embrittlement effect simultaneously, therefore wish their content to be reduced to minimum level.H≤3ppm, O≤30ppm, N≤50ppm in application claims steel.
The manufacture method of pressurized-water reactor nuclear power plant potentiostat steel of the present invention comprises following technique, and steel plate thickness is 20-100mm:
1, the smelting of steel:
For the steel plate of thickness <70mm, Deep Desulphurization of Hot Metal, converter smelting, external refining, vacuum-treat and continuous casting working procedure is adopted to produce;
For the steel plate of thickness >=70mm, electric furnace, external refining, vacuum-treat and die casting cast operation is adopted to produce.
2, steel plate rolling:
For continuously cast bloom, adopt controlled rolling technology, billet heating temperature at 1150 ~ 1250 DEG C, rolling finishing temperature >=1000 DEG C, recrystallization zone, Unhydrated cement rolling temperature controls at 830 ~ 880 DEG C, and rolling total reduction is greater than 70%, rolls rear naturally cooling;
For static ingot, after batch-type furnace heating, adopt ingot stocking mode to produce, Heating Steel Ingots temperature >=1200 DEG C, start rolling temperature >=1050 DEG C, roll rear naturally cooling.
3, modifier treatment:
Steel plate rolls rear employing modifier treatment technique, to obtain careful, uniform sorbite tissue, and makes steel plate have good comprehensive mechanical property.
Modifier treatment technique is: quenching temperature 850 ~ 930 DEG C, soaking time 2-4min/mm; Tempering temperature 630 ~ 680 DEG C, soaking time 4-10min/mm.
Compared with prior art, beneficial effect is as follows for the pressurized-water reactor nuclear power plant potentiostat steel adopting the present invention to produce:
(1) product of the present invention has excellent intensity index.For 60mm plate, after modifier treatment, yield strength (Rel) and tensile strength (Rm) are respectively 550N/mm 2and 675N/mm 2(index request Rel>=450N/mm 2, Rm:620-795N/mm 2); After Simulated post-weld heat treatment, yield strength (Rel) and tensile strength (Rm) are respectively 510N/mm 2and 645N/mm 2(index request Rel>=450N/mm 2, Rm:620-795N/mm 2); After modifier treatment during 350 DEG C of drawing by high temperature, yield strength (Rel) and tensile strength (Rm) are respectively 490N/mm 2and 665N/mm 2(index request Rel>=380N/mm 2, Rm>=560N/mm 2); After Simulated post-weld heat treatment, yield strength (Rel) and tensile strength (Rm) are respectively 440N/mm 2and 600N/mm 2(index request Rel>=380N/mm 2, Rm>=560N/mm 2).Room temperature tensile and drawing by high temperature result after modifier treatment and Simulated post-weld heat treatment, different states steel plate stretching performance, far above index request, has a more substantial increase compared to other steel grade.
(2) steel grade of the present invention is after modifier treatment, and-20 DEG C of shock absorption energy under different states remain on higher level equally.For 60mm plate, the shock absorption energy after modifier treatment and Simulated post-weld heat treatment, between 210-250J, meets the requirement of index completely, and has larger surplus.
Embodiment
Below by embodiment, the present invention is further illustrated.
The chemical composition of embodiment of the present invention steel is as shown in table 1.
The chemical composition (wt%) of table 1 various embodiments of the present invention steel
Embodiment 1
The pressurized-water reactor nuclear power plant potentiostat steel of the present embodiment, molten steel, through converter smelting, external refining, vacuum-treat, is cast into the continuously cast bloom of thickness 300mm, and mill product steel plate specification is that its chemical composition of 20mm(is in table 1).Its rolling and thermal treatment process are in table 2, and mechanical property is in table 3.
The rolling of table 2 embodiment of the present invention 1 steel and thermal treatment process
The mechanical property result of table 3 embodiment of the present invention 1 steel
From table 3,20mm specification steel plate of the present invention is after modifier treatment and Simulated post-weld heat treatment, each performance index meet the demands completely, and steel plate has good high-temperature behavior and good toughness, strength matching simultaneously, meets the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.
Embodiment 2
The pressurized-water reactor nuclear power plant potentiostat steel of the present embodiment, molten steel is through converter smelting, external refining (LF, VD) process, and be cast into the continuously cast bloom of thickness 300mm, mill product steel plate specification is that its chemical composition of 40mm(is in table 1).Its rolling and thermal treatment process are in table 4, and mechanical property is in table 5.
The rolling of table 4 embodiment of the present invention 2 steel and thermal treatment process
The mechanical property result of table 5 embodiment of the present invention 2 steel
From table 5,40mm specification steel plate of the present invention is after modifier treatment and Simulated post-weld heat treatment, each performance index meet the demands completely, and the tensile strength of steel plate is close to the middle upper limit, illustrate that steel plate has excellent intensity and impelling strength, meet the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.
Embodiment 3
The pressurized-water reactor nuclear power plant potentiostat steel of the present embodiment, molten steel is through converter smelting, external refining (LF, VD) process, and be cast into the continuously cast bloom of thickness 300mm, mill product steel plate specification is that its chemical composition of 60mm(is in table 1).Its rolling and thermal treatment process are in table 6, and mechanical property is in table 7.
The rolling of table 6 embodiment of the present invention 3 steel and thermal treatment process
The mechanical property result of table 7 embodiment of the present invention 3 steel
From table 7,60mm specification steel plate of the present invention is after modifier treatment and Simulated post-weld heat treatment, and each performance index meet the demands completely, and has certain surplus, meets the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.
Embodiment 4
The pressurized-water reactor nuclear power plant potentiostat steel of the present embodiment, molten steel, through electrosmelting, external refining (LF, VD) process, is cast into the steel ingot of thickness 610mm, and adopting Rolling from Ingot to make specification is 70mm steel plate (its chemical composition is in table 1).Its rolling and thermal treatment process are in table 8, and mechanical property is in table 9.
The rolling of table 8 embodiment of the present invention 4 steel and thermal treatment process
The mechanical property result of table 9 embodiment of the present invention 4 steel
From table 9,70mm specification steel plate of the present invention is after modifier treatment and Simulated post-weld heat treatment, and each performance index meet the demands completely, and has certain surplus, meets the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.
Embodiment 5
The pressurized-water reactor nuclear power plant potentiostat steel of the present embodiment, molten steel, through electrosmelting, external refining (LF, VD) process, be cast into the steel ingot of thickness 610mm, and to adopt Rolling from Ingot to make specification is 100mm steel plate (its chemical composition is in table 1).Its rolling and thermal treatment process are in table 10, and mechanical property is in table 11.
The rolling of table 10 embodiment of the present invention 5 steel and thermal treatment process
The mechanical property result of table 11 embodiment of the present invention 5 steel
From table 11,100mm specification steel plate of the present invention is after modifier treatment and Simulated post-weld heat treatment, and each performance index meet the demands completely, and has certain surplus, meets the requirement of pressurized-water reactor nuclear power plant potentiostat steel completely.

Claims (1)

1. the manufacture method of a pressurized-water reactor nuclear power plant potentiostat steel, the components based on weight percentage of this pressurized-water reactor nuclear power plant potentiostat steel: C0.10%-0.25%, Si0.15%-0.35%, Mn0.80%-0.95%, P≤0.010%, S≤0.010%, Ni0.50%-0.80%, Cr0.20%-0.60%, Al0.005%-0.040%, Mo0.40%-0.70%, V0.005-0.008%, Ti0.005-0.01%, Cu≤0.10%, surplus is Fe and inevitable impurity, it is characterized in that comprising following technique: 1) smelt: for the steel plate of thickness <70mm, adopt Deep Desulphurization of Hot Metal, converter smelting, external refining, vacuum-treat and continuous casting working procedure, for the steel plate of thickness >=70mm, adopt electric furnace, external refining, vacuum-treat and die casting cast operation, 2) rolling: for continuously cast bloom, adopt controlled rolling technology, billet heating temperature is 1150 ~ 1250 DEG C, rolling finishing temperature >=1000 DEG C, recrystallization zone, it is 830 ~ 880 DEG C that Unhydrated cement rolling temperature controls, and rolling total reduction is greater than 70%, rolls rear naturally cooling, for static ingot, after batch-type furnace heating, adopt ingot stocking mode to produce, Heating Steel Ingots temperature >=1200 DEG C, start rolling temperature >=1050 DEG C, roll rear naturally cooling, 3) modifier treatment: steel plate rolls rear quenching temperature 850 ~ 930 DEG C, soaking time 2-4min/mm, tempering temperature 630 ~ 680 DEG C, soaking time 4-10min/mm.
CN201210092194.3A 2012-03-30 2012-03-30 A kind of pressurized-water reactor nuclear power plant potentiostat steel and manufacture method thereof CN103361567B (en)

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