CN103160732A - Steel for nuclear power pressure-bearing equipment and manufacturing method thereof - Google Patents
Steel for nuclear power pressure-bearing equipment and manufacturing method thereof Download PDFInfo
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- CN103160732A CN103160732A CN2011104173608A CN201110417360A CN103160732A CN 103160732 A CN103160732 A CN 103160732A CN 2011104173608 A CN2011104173608 A CN 2011104173608A CN 201110417360 A CN201110417360 A CN 201110417360A CN 103160732 A CN103160732 A CN 103160732A
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- 229910000831 Steel Inorganic materials 0.000 title claims abstract description 113
- 239000010959 steel Substances 0.000 title claims abstract description 113
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 17
- 238000005096 rolling process Methods 0.000 claims abstract description 26
- 238000000034 method Methods 0.000 claims abstract description 20
- 238000010438 heat treatment Methods 0.000 claims abstract description 13
- 238000003723 Smelting Methods 0.000 claims abstract description 8
- 230000008569 process Effects 0.000 claims abstract description 7
- 238000010791 quenching Methods 0.000 claims abstract description 4
- 230000000171 quenching effect Effects 0.000 claims abstract description 4
- 238000005496 tempering Methods 0.000 claims abstract description 4
- 239000012535 impurity Substances 0.000 claims abstract 2
- 239000003607 modifier Substances 0.000 claims description 10
- 238000007670 refining Methods 0.000 claims description 9
- 238000001953 recrystallisation Methods 0.000 claims description 8
- 238000002791 soaking Methods 0.000 claims description 6
- 238000001816 cooling Methods 0.000 claims description 4
- 235000013399 edible fruits Nutrition 0.000 claims description 3
- 238000003860 storage Methods 0.000 claims description 3
- 238000009749 continuous casting Methods 0.000 claims description 2
- 230000001186 cumulative effect Effects 0.000 claims description 2
- 238000004512 die casting Methods 0.000 claims description 2
- 229910052698 phosphorus Inorganic materials 0.000 claims description 2
- 230000003068 static effect Effects 0.000 claims description 2
- 229910052717 sulfur Inorganic materials 0.000 claims description 2
- -1 rolling Substances 0.000 claims 2
- 239000000126 substance Substances 0.000 abstract description 9
- 238000010521 absorption reaction Methods 0.000 abstract description 4
- 229910052755 nonmetal Inorganic materials 0.000 abstract description 2
- 238000007669 thermal treatment Methods 0.000 description 19
- 239000000203 mixture Substances 0.000 description 13
- 239000000463 material Substances 0.000 description 10
- 238000004088 simulation Methods 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 5
- 239000013078 crystal Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 230000035939 shock Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000005204 segregation Methods 0.000 description 2
- 229910000975 Carbon steel Inorganic materials 0.000 description 1
- CWYNVVGOOAEACU-UHFFFAOYSA-N Fe2+ Chemical compound [Fe+2] CWYNVVGOOAEACU-UHFFFAOYSA-N 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 238000005275 alloying Methods 0.000 description 1
- 229910001566 austenite Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000010962 carbon steel Substances 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000005728 strengthening Methods 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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Abstract
The invention discloses steel for nuclear power pressure equipment and a manufacturing method thereof, wherein the steel comprises the following chemical components in percentage by weight: 0.12% -0.18% of C; 0.15% -0.35% of Si; 1.20-1.65% Mn; p is less than or equal to 0.015 percent; s is less than or equal to 0.010 percent; 0.50% -0.85% of Ni; cr is less than or equal to 0.15 percent; 0.020-0.050% of Al; v is less than or equal to 0.02 percent; ti less than or equal to 0.02 percent, the balance of Fe and inevitable impurities, and simultaneously controlling non-metallic inclusions in the steel to ensure that A, B, C, D type inclusions are less than or equal to 1.5 grade. The manufacturing method mainly comprises the steps of steel smelting, rolling and quenching and tempering. The invention further optimizes the chemical components and the heat treatment process, reduces the gas and nonmetal inclusions in the steel, ensures that the mechanical properties of the steel plate in a heat treatment state, a simulated postweld heat treatment state and a high temperature state of 200 ℃ are kept at a higher level, and completely meets the requirements of technical indexes; meanwhile, the impact absorption energy at 0 ℃ is still kept at a higher level, better matching of the strength and the toughness of the steel plate is reflected, and the steel plate is completely suitable for the requirements of steel for nuclear power pressure-bearing equipment.
Description
Technical field
The invention belongs to the ferrous material field, particularly steel for nuclear power pressure equipment and manufacture method thereof.
Background technology
Along with the countries in the world rapid development of economy, nuclear energy more and more is subject to the attention of various countries as a kind of cleaning, safe, the stable energy, safe utilization nuclear energy, greatly develops nuclear power and has become a kind of trend.And in the nuclear power technology application facet, significant progress has been arranged also, and from original " two generations " technology, develop into present " two generations added " and " three generations " technology, make safety performance that larger raising arranged.
In numerous nuclear power generating sets that foundation different IPs power technology is built, steel for nuclear power pressure equipment plays a part very important as the propping material of the visual plants such as support core reactor pressure vessel, potentiostat, various pipeline, case, groove, tank.The stable of the safety of its operation, performance will directly have influence on whole unit safety work.
At present, material as steel for nuclear power pressure equipment is more, as: A42, A52, P295GH, P355GH and S355J0 etc., above-mentioned steel grade is carbon steel substantially, tensile strength mostly is controlled between 400-550MPa, can effectively reduce due to the adding of alloying element the radiation embrittlement effect that causes.But as bearing device, also needing to stand long-time stress-removal processes, also to check its high temperature tensile properties, and the intensity of above-mentioned steel grade after long-time stress-removal is processed or under the condition of high temperature all has decline in various degree, be difficult to meet the demands, be only applicable to make the propping material of nuclear power support equipment, utility appliance, far can not satisfy the demand that existing " two generations added " and " three generations " nuclear power generating sets nuclear island key equipment pressure-bearing are used steel.As thickness of slab be the S355J0 steel plate of 60mm after normalizing treatment, yield strength (Rel) and tensile strength (Rm) are respectively 360N/mm
2And 525N/mm
2(index request Rel 〉=330N/mm
2, Rm 〉=510N/mm
2); After the simulation postweld heat treatment, yield strength (Rel) and tensile strength (Rm) are respectively 340N/mm
2And 500N/mm
2(index request Rel 〉=330N/mm
2, Rm 〉=510N/mm
2); During 200 ℃ of drawing by high temperature, yield strength (Rel) and tensile strength (Rm) are respectively 255N/mm
2And 470N/mm
2From three processes, steel plate is after normalizing treatment, and intensity satisfies index request fully, and has certain surplus.But after the simulation postweld heat treatment, armor plate strength descends obviously, and especially tensile strength can not satisfy index request; In the time of 200 ℃, the intensity of steel plate, especially yield strength descend more obvious, show that this steel grade high-temperature resistance is relatively low, can not satisfy the demand that the nuclear power key equipment is built.
Summary of the invention
The invention provides a kind of steel for nuclear power pressure equipment and manufacture method thereof, by gas and nonmetal inclusion in further optimization chemical composition, thermal treatment process, reduction steel, make steel plate all keep higher level in the mechanical property of as-heat-treated condition, simulation postweld heat treatment state and 200 ℃ of conditions of high temperature, satisfy the requirement of technical indicator fully; Simultaneously 0 ℃ of shock absorption energy still remains on higher level, embodies the coupling of armor plate strength and toughness preferably, is applicable to the demand of steel for nuclear power pressure equipment fully.
A kind of core steel for nuclear power pressure equipment provided by the invention and manufacture method thereof can solve the problem that prior art exists, and concrete technical scheme is:
Steel for nuclear power pressure equipment comprises the C of following component: 0.12%-0.18% by weight percentage; The Si of 0.15%-0.35%; The Mn of 1.20%-1.65%; ≤ 0.015% P; ≤ 0.010% S; The Ni of 0.50%-0.85%; ≤ 0.15% Cr; The Al of 0.020%-0.050%; ≤ 0.02% V; ≤ 0.02% Ti, all the other content are Fe.
The present invention also requires H≤1.5ppm in steel, O≤30ppm.
Control simultaneously nonmetallic inclusionsin steel, guarantee that A, B, C, D class are mingled with≤1.5 grades (A tests by ASTM E45 method, and is lower same).
Adopt the mentioned component design the reasons are as follows:
(1) C: in steel, C content is the principal element that guarantees armor plate strength, C content is on the low side, intensity may can not meet requirement, especially reach through long-time simulation postweld heat treatment and move under 200 ℃ of high temperature, intensity all will get decline to a certain extent, therefore the present invention requires that in steel, C content should be controlled at 0.12%-0.18%, is preferably 0.14%-0.18%.
(2) Si:Si is effective strengthening element, is also simultaneously cheap element, and therefore same collateral security steel plate different steps Strength Changes all can satisfy the index request angle and consider, Si content is controlled at 0.15%-0.35%, is preferably 0.20%-0.35%.
(3) Mn: in steel, the Mn element is strengthened the matrix effect except plaing, and can also effectively improve the hardening capacity of steel, so in the actual production steel, Mn content is controlled at 1.20%-1.65%, is preferably 1.35%-1.65%.
(4) Ni:Ni can obviously improve the low-temperature flexibility of steel, improve simultaneously the low-temperature flexibility (the especially above steel plate of 100mm) of thick cross section steel plate, make steel plate also can have higher toughness when having sufficient intensity, satisfy the requirement of index, therefore from actual needs, the present invention requires that in steel, Ni content is controlled at 0.50%-0.85%, is preferably 0.65%-0.85%.
(5) Cr:Cr can significantly improve the antioxygenation of steel in steel, increases resistance to corrosion.Dwindle simultaneously the austenite phase region, 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≤0.15% in steel, is preferably 0.05%-0.15%.
The nitrogen agent is decided in deoxidation when (6) Al:Al is mainly used in making steel in steel, and can crystal grain thinning, prevents the timeliness of soft steel, improves steel in low-temperature flexibility, and Al content is too much unsuitable simultaneously, in order to avoid produce Al
2O
3Be mingled with.Usually the Al content in steel is controlled at 0.020%-0.050%, is preferably 0.020%-0.035%.
(6) V, Ti: it is fine grained steel that nuclear power requires with steel, fine grained steel is less than coarse-grained steel irradiation fragility, add V, Ti that crystal grain thinning is arranged in steel, improve the grain coarsening temperature action, so V, Ti content requirement≤0.02% in steel, be preferably 0.005%-0.02%.
(7) P: irradiation test shows, P is also very responsive to radiation embrittlement, and P content is higher simultaneously, also be easy to aggravate the generation of center segregation and center porosity in steel, therefore require the P content in steel more low better, be controlled to be≤0.015%, preferred requirement≤0.010%.
(8) S:S forms the S compound and is mingled with in steel, has reduced the impelling strength of steel, affects welding property, aggravate simultaneously the generation of center segregation, the defective such as loose, therefore require that in steel, S content should be more low better, be controlled to be≤0.010%, preferably require≤0.003%.
(9) gas H, O: generally speaking, they are all harmful to the performance of steel, also can increase the radiation embrittlement effect simultaneously, therefore wish will be reduced to minimum level to their content.The present invention requires H≤1.5ppm in steel, O≤30ppm.
Realize that the present invention takes following technical measures on production technique:
The smelting aspect of steel:
The employing converter of steel plate thickness≤80mm, continuous casting process are produced; The employing electric furnace of steel plate thickness＞80mm, die casting process are produced.Adopt external refining and Fruit storage in production process.
The rolling aspect of steel plate:
Continuously cast bloom adopt the recrystallization zone and non-recrystallization district two-stage control rolling, billet heating temperature is at 1150～1200 ℃, the rolling finishing temperature in recrystallization zone 〉=1000 ℃, and non-recrystallization district rolling temperature is controlled at 850 ± 20 ℃, cumulative deformation 〉=50% rolls rear naturally cooling;
Static ingot adopts ingot stocking mode to produce, and the Heating Steel Ingots temperature adopts high temperature to roll soon at 1150～1200 ℃ in the operation of rolling, roll rear naturally cooling.
Need after steel plate rolls to carry out modifier treatment, make organize more evenly, crystal grain is more tiny, performance is more stable.
Modifier treatment technique is: 940 ± 10 ℃ of quenching temperatures, soaking time 2-3min/mm, 590 ± 10 ℃ of tempering temperatures, soaking time 2-4min/mm.
The invention provides a kind of steel for nuclear power pressure equipment and manufacture method thereof, the steel plate thickness of production is 20-120mm, and width and length can be produced according to the actual requirements.Compared with prior art, beneficial effect is as follows:
(1) steel grade of the present invention after modifier treatment, all has strength level preferably under different states.Steel plate is through modifier treatment, yield strength (Rel) 〉=400N/mm
2, tensile strength (Rm) is at 560-625N/mm
2Between; After the simulation postweld heat treatment, yield strength (Rel) 〉=360N/mm
2, tensile strength (Rm) is at 530-600N/mm
2Between; During 200 ℃ of drawing by high temperature, yield strength (Rel) 〉=340N/mm
2, tensile strength (Rm) is at 510-580N/mm
2Between.From three states, the armor plate strength fall is all less, and different states all can satisfy index request.Had significantly than other steel grades and improved.
(2) steel grade of the present invention is after modifier treatment, and 0 ℃ of shock absorption energy under different states remains on higher level equally.Shock absorption energy after steel plate modifier treatment and simulation postweld heat treatment not only satisfies the requirement of index, and has larger surplus more than all remaining on 200J.
Embodiment
A kind of steel for nuclear power pressure equipment and manufacture method embodiment thereof are as follows:
Embodiment one
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through converter smelting, external refining (LF, VD), is cast into continuously cast bloom, and mill product steel plate specification is 20mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 1,2,3.
Table 1 chemical composition (%)
Rolling and the thermal treatment process of table 2
Table 3 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 0.5 grade of category-A, 0.5 grade of category-B, 0.5 grade of C class, 1.0 grades of D classes.
By to different states mechanical properties test after the thermal treatment of 20mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Embodiment two
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through converter smelting, external refining (LF, VD), is cast into continuously cast bloom, and mill product steel plate specification is 40mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 4,5,6.
Table 4 chemical composition (%)
Rolling and the thermal treatment process of table 5
Table 6 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 0.5 grade of category-A, 1.0 grades of category-Bs, 0.5 grade of C class, 1.0 grades of D classes.
By to different states mechanical properties test after the thermal treatment of 40mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Embodiment three
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through converter smelting, external refining (LF, VD), is cast into continuously cast bloom, and mill product steel plate specification is 60mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 7,8,9.
Table 7 chemical composition (%)
Rolling and the thermal treatment process of table 8
Table 9 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 0.5 grade of category-A, 1.5 grades of category-Bs, 0.5 grade of C class, 1.0 grades of D classes.
By to different states mechanical properties test after the thermal treatment of 60mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Embodiment four
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through converter smelting, external refining (LF, VD), is cast into continuously cast bloom, and mill product steel plate specification is 80mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 10,11,12.
Table 10 chemical composition (%)
Rolling and the thermal treatment process of table 11
Table 12 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 1.0 grades of category-As, 1.0 grades of category-Bs, 0.5 grade of C class, 0.5 grade of D class.
By to different states mechanical properties test after the thermal treatment of 80mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Embodiment five
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through electrosmelting, external refining (LF, VD), be cast into steel ingot, and Direct Rolling finished steel plate specification is 100mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 13,14,15.
Table 13 chemical composition (%)
Rolling and the thermal treatment process of table 14
Table 15 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 0.5 grade of category-A, 1.0 grades of category-Bs, 0.5 grade of C class, 1.0 grades of D classes.
By to different states mechanical properties test after the thermal treatment of 100mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Embodiment six
The steel for nuclear power pressure equipment of the present embodiment, molten steel is processed through electrosmelting, external refining (LF, VD), be cast into steel ingot, and Direct Rolling finished steel plate specification is 120mm.Its composition, rolling and thermal treatment process, mechanical property result see Table respectively shown in 16,17,18.
Table 16 chemical composition (%)
Rolling and the thermal treatment process of table 17
Table 18 mechanical property result
Check simultaneously nonmetallic inclusionsin steel: 0.5 grade of category-A, 1.5 grades of category-Bs, 0.5 grade of C class, 1.5 grades of D classes.
By to different states mechanical properties test after the thermal treatment of 120mm plate, its result all satisfies the requirement of index, and has certain affluence amount, satisfies the requirement of nuclear power pressure equipment material fully.
Claims (4)
1. steel for nuclear power pressure equipment is characterized in that comprising by weight percentage the C of following component: 0.12%-0.18%; The Si of 0.15%-0.35%; The Mn of 1.20%-1.65%; ≤ 0.015% P; ≤ 0.010% S; The Ni of 0.50%-0.85%; ≤ 0.15% Cr; The Al of 0.020%-0.050%; ≤ 0.02% V; ≤ 0.02% Ti, all the other content are Fe and inevitable impurity, control simultaneously H≤1.5ppm in steel, O≤30ppm, non-metallic inclusion guarantee A, B, C, D class be mingled with≤1.5 grades.
2. a kind of steel for nuclear power pressure equipment according to claim 1 is characterized in that comprising by weight percentage the C of following component: 0.14%-0.18%; The Si of 0.20%-0.35%; The Mn of 1.35%-1.65%; The Ni of 0.65%-0.85%; The Cr of 0.05%-0.15%; The Al of 0.020%-0.035%; The V of 0.005%-0.02%; The Ti of 0.005%-0.02%.
3. manufacture method that is used for steel for nuclear power pressure equipment claimed in claim 1, mainly comprise the smelting of steel, rolling, modifier treatment, the employing converter, the continuous casting process that it is characterized in that steel plate thickness≤80mm are produced, and adopt external refining and Fruit storage in production process; Continuously cast bloom adopt the recrystallization zone and non-recrystallization district two-stage control rolling, billet heating temperature is at 1150～1200 ℃, the rolling finishing temperature in recrystallization zone 〉=1000 ℃, and non-recrystallization district rolling temperature is controlled at 850 ± 20 ℃, cumulative deformation 〉=50% rolls rear naturally cooling; Modifier treatment technique is: 940 ± 10 ℃ of quenching temperatures, soaking time 2-3min/mm, 590 ± 10 ℃ of tempering temperatures, soaking time 2-4min/mm.
4. manufacture method that is used for steel for nuclear power pressure equipment claimed in claim 1, mainly comprise the smelting of steel, rolling, modifier treatment, the employing electric furnace, the die casting process that it is characterized in that steel plate thickness＞80mm are produced, and adopt external refining and Fruit storage in production process; Static ingot adopts ingot stocking mode to produce, and the Heating Steel Ingots temperature adopts high temperature to roll soon at 1150～1200 ℃ in the operation of rolling, roll rear naturally cooling; Modifier treatment technique is: 940 ± 10 ℃ of quenching temperatures, soaking time 2-3min/mm, 590 ± 10 ℃ of tempering temperatures, soaking time 2-4min/mm.
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104561824A (en) * | 2013-10-10 | 2015-04-29 | 鞍钢股份有限公司 | Steel for nuclear-grade equipment support and manufacturing method thereof |
| CN107287509A (en) * | 2016-03-31 | 2017-10-24 | 鞍钢股份有限公司 | Steel for 550 MPa-grade nuclear power voltage stabilizer equipment and manufacturing method thereof |
| CN107287500A (en) * | 2016-03-31 | 2017-10-24 | 鞍钢股份有限公司 | Steel for pressurized water reactor nuclear power station safety injection tank base plate and manufacturing method thereof |
| CN107746937A (en) * | 2017-11-22 | 2018-03-02 | 武汉钢铁有限公司 | High-strength high-toughness steel plate and its manufacture method for nuclear power pressure equipment |
| CN108546878A (en) * | 2018-05-11 | 2018-09-18 | 鞍钢股份有限公司 | Steel for supporting thick nuclear power steam generator and production method thereof |
| CN108660382A (en) * | 2017-03-29 | 2018-10-16 | 鞍钢股份有限公司 | Steel with excellent radiation resistance for steel lining of nuclear power station and manufacturing method thereof |
| CN109554610A (en) * | 2017-09-27 | 2019-04-02 | 鞍钢股份有限公司 | Steel plate for nuclear power safety injection tank and production process thereof |
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| CN102181807A (en) * | 2011-05-09 | 2011-09-14 | 武汉钢铁(集团)公司 | Steel for nuclear power pressure equipment at temperature of -50 DEG C and manufacturing method thereof |
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2011
- 2011-12-14 CN CN201110417360.8A patent/CN103160732B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102181807A (en) * | 2011-05-09 | 2011-09-14 | 武汉钢铁(集团)公司 | Steel for nuclear power pressure equipment at temperature of -50 DEG C and manufacturing method thereof |
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| CN104561824A (en) * | 2013-10-10 | 2015-04-29 | 鞍钢股份有限公司 | Steel for nuclear-grade equipment support and manufacturing method thereof |
| CN107287509A (en) * | 2016-03-31 | 2017-10-24 | 鞍钢股份有限公司 | Steel for 550 MPa-grade nuclear power voltage stabilizer equipment and manufacturing method thereof |
| CN107287500A (en) * | 2016-03-31 | 2017-10-24 | 鞍钢股份有限公司 | Steel for pressurized water reactor nuclear power station safety injection tank base plate and manufacturing method thereof |
| CN108660382A (en) * | 2017-03-29 | 2018-10-16 | 鞍钢股份有限公司 | Steel with excellent radiation resistance for steel lining of nuclear power station and manufacturing method thereof |
| CN109554610A (en) * | 2017-09-27 | 2019-04-02 | 鞍钢股份有限公司 | Steel plate for nuclear power safety injection tank and production process thereof |
| CN109694984B (en) * | 2017-10-20 | 2021-04-27 | 鞍钢股份有限公司 | Steel for ultra-thick nuclear reactor containment gate and manufacturing method thereof |
| CN109694984A (en) * | 2017-10-20 | 2019-04-30 | 鞍钢股份有限公司 | Steel for ultra-thick nuclear reactor containment gate and manufacturing method thereof |
| CN107746937A (en) * | 2017-11-22 | 2018-03-02 | 武汉钢铁有限公司 | High-strength high-toughness steel plate and its manufacture method for nuclear power pressure equipment |
| CN108546878A (en) * | 2018-05-11 | 2018-09-18 | 鞍钢股份有限公司 | Steel for supporting thick nuclear power steam generator and production 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 |
| CN111270145A (en) * | 2020-03-19 | 2020-06-12 | 鞍钢股份有限公司 | Ultra-thick high-strength steel plate for nuclear power station containment penetration piece and production method thereof |
| CN111394547B (en) * | 2020-03-19 | 2022-05-17 | 鞍钢股份有限公司 | Ultra-thick high-strength steel for nuclear reactor containment vessel and manufacturing method thereof |
| CN111321349A (en) * | 2020-03-30 | 2020-06-23 | 南京钢铁股份有限公司 | 130mm containment nuclear power steel and continuous casting billet low-compression-ratio manufacturing method thereof |
| CN111321349B (en) * | 2020-03-30 | 2022-04-19 | 南京钢铁股份有限公司 | 130mm containment nuclear power steel and continuous casting billet low-compression-ratio 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 |
| CN113106210A (en) * | 2021-03-01 | 2021-07-13 | 江阴兴澄特种钢铁有限公司 | Manufacturing method of P355GH-Z35 steam pocket steel plate with thickness specification of more than 200mm |
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