CN103820728B - Nuclear power station CRDM detachable fitting and preparation method thereof - Google Patents

Nuclear power station CRDM detachable fitting and preparation method thereof Download PDF

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Publication number
CN103820728B
CN103820728B CN201410062565.2A CN201410062565A CN103820728B CN 103820728 B CN103820728 B CN 103820728B CN 201410062565 A CN201410062565 A CN 201410062565A CN 103820728 B CN103820728 B CN 103820728B
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crdm
preparation
detachable fitting
hours
esr ingot
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CN103820728A (en
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杨春乐
杨孟嘉
陈志强
冉小兵
邓小云
戴长年
刘宝亭
米大为
唐茂
吴昊
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
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Abstract

The invention discloses the preparation method of a kind of nuclear power station CRDM detachable fitting, it comprises the following steps: 1) choose raw material vacuum metling, it is thus achieved that molten steel;2) pouring molten steel electrode is used;3) electrode electroslag remelting is obtained ESR ingot, wherein, by weight percentage, ESR ingot contains 0.080 0.140%C ,≤0.50%Si ,≤0.80%Mn ,≤0.020%S ,≤0.030%P, 0.50 1.00%Ni, 11.50 13.00%Cr ,≤0.10%Co ,≤0.050%Al ,≤0.60%Mo and surplus Fe;4) hammer cogging after ESR ingot being made annealing treatment;5) after annealing billet processes, after hot rolled round steel, round steel Tempering and Quenching and ultrasonic inspection obtain nuclear power station CRDM detachable fitting.The CRDM detachable fitting that method produced according to the present invention obtains is by optimizing chemical analysis and technique, CRDM detachable fitting safe operation under conditions of use, during the clutch partially-working of end in elastic range, plastic deformation will not occur, life-span meets design specification and the national standard requirement of CRDM, it is achieved that the production domesticization that CRDM detachable fitting manufactures.

Description

Nuclear power station CRDM detachable fitting and preparation method thereof
Technical field
The invention belongs to technical field of nuclear power, it is more particularly related to a kind of nuclear power station control rod drives Motivation structure detachable fitting and preparation method thereof.
Background technology
Nuclear Power Station safety class equipment--CRDM (CRDM) is important in nuclear power plant reactor system Plant equipment, as the some of reactor control and protection system, CRDM is extremely important execution Mechanism, its major function is to drive control rod upper and lower motion in reactor core to realize reactor start-up, hoisting work Rate, holding power, Steam Generator in Load Follow, normal shutdown and breakdown.
Nuclear power station CRDM detachable fitting is used for connecting drive-rod part and C&P systems, and needs have enough Intensity and impact resistance, it is impossible to produce fracture, the one end especially worked has the effect of clutch, There is the most elastic and high yield strength.
But, nuclear power station CRDM detachable fitting is monopolized by external a few countries for a long time, and they control for a long time Make the CRDM detachable fitting supply of material market of whole world nuclear power projects.External minority CRDM that places one's entire reliance upon sets Standby manufacturer supplies, and China not only needs to pay more the purchase cost of costliness, and delivery cycle is uncertain, Risk is big, can affect China in various degree and build the duration progress of nuclear power new projects.
In view of this, a kind of nuclear power station CRDM detachable fitting of necessary offer and preparation side thereof Method.
Summary of the invention
The goal of the invention of the present invention is: provide a kind of nuclear power station CRDM detachable fitting and system thereof Preparation Method.
In order to realize foregoing invention purpose, the invention provides a kind of nuclear power station CRDM being disconnected The preparation method of head, it comprises the following steps:
1) raw material vacuum metling are chosen, it is thus achieved that molten steel;
2) pouring molten steel electrode is used;
3) electrode electroslag remelting being obtained ESR ingot, wherein, by weight percentage, ESR ingot contains 0.080-0.140%C、≤0.50%Si、≤0.80%Mn、≤0.020%S、≤0.030%P、0.50-1.00%Ni、 11.50-13.00%Cr ,≤0.10%Co ,≤0.050%Al ,≤0.60%Mo and surplus Fe;
4) hammer cogging after ESR ingot being made annealing treatment;
5) after annealing billet processes, after hot rolled round steel, round steel Tempering and Quenching and ultrasonic inspection obtain nuclear power Stand CRDM detachable fitting.
As a kind of improvement of preparation method of the present invention, step 1) in, vacuum during vacuum metling reaches 2.7x10-2Mbar, and first at loading alloy material in addition to metal Mn in vaccum sensitive stove, after being filled with argon Metal Mn is added by auto feed room.
As a kind of improvement of preparation method of the present invention, step 1) in, each element uses pure material to allocate into.
As a kind of improvement of preparation method of the present invention, step 4) in, the annealing process of ESR ingot is :≤ 600 DEG C are incubated about 3 hours, are heated to the firing rate of≤120 DEG C/h > 840 DEG C;> 840 DEG C of insulations about 6 After hour, cool down with the rate of cooling of≤50 DEG C/h.
As a kind of improvement of preparation method of the present invention, step 4) in, the heating during hammer cogging of ESR ingot Technique is: by ESR ingot after≤600 DEG C of insulations about 3 hours, heats with the firing rate of≤120 DEG C/h To > 1100 DEG C and > 1100 DEG C of insulations 6 hours.
As a kind of improvement of preparation method of the present invention, step 5) in, the annealing process of steel billet is: 600~650 DEG C, after expecting, are heated to 860 DEG C ± 10 DEG C with the firing rate of≤120 DEG C/h;At 860 DEG C ± 10 DEG C After being incubated 5~6 hours, it is cooled to 400 DEG C with the rate of cooling of 20~40 DEG C/h and comes out of the stove.
As a kind of improvement of preparation method of the present invention, step 5) in, the concrete technology of round steel Tempering and Quenching For: quenching, it is incubated about 0.5 hour at≤650 DEG C, then heating is warming up to 960~1000 DEG C in 4~5 hours; After 960~1000 DEG C of insulations 1~1.2 hour, oil quenching;Tempering, is incubated about 0.5 hour at≤650 DEG C, so Post-heating 1.5~be warming up to 660~680 DEG C in 2 hours;After 660~680 DEG C of insulations 3~3.5 hours, air cooling.
As a kind of improvement of preparation method of the present invention, step 4) in ESR ingot annealing after, sampling is really Alloying component and the content of recognizing ESR ingot are step 3) in alloying component and content.
In order to realize foregoing invention purpose, present invention also offers a kind of nuclear power station CRDM removable Joint, by weight percentage, described nuclear power station CRDM detachable fitting containing 0.080-0.140%C, ≤0.50%Si、≤0.80%Mn、≤0.020%S、≤0.030%P、0.50-1.00%Ni、11.50-13.00%Cr、 ≤ 0.10%Co ,≤0.050%Al ,≤0.60%Mo and surplus Fe.
As a kind of improvement of nuclear power station CRDM detachable fitting of the present invention, described nuclear power station controls Rod drive mechanism detachable fitting is obtained by aforementioned preparation process.
Relative to prior art, nuclear power station CRDM detachable fitting of the present invention and preparation method thereof has Have the advantage that
1. by optimizing chemical analysis and technique, CRDM detachable fitting under conditions of use can safe operation, During the clutch partially-working of end in elastic range, plastic deformation not occurring, the life-span meets setting of CRDM Meter specification and national standard requirement, it is achieved that the production domesticization that CRDM detachable fitting manufactures.
2., when being arranged in CRDM operation, safe and reliable, the especially clutch configuration of end has sufficiently Elastic.
3. can utilize domestic existing process equipment processing and manufacturing, there is no technologic difficulty, be beneficial to batch raw Produce, accelerate localization process.
Accompanying drawing explanation
Below in conjunction with the accompanying drawings and embodiment, to nuclear power station CRDM detachable fitting of the present invention and system thereof Preparation Method is described in detail, in accompanying drawing:
Fig. 1 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, vacuum metling Artwork.
Fig. 2 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, moving back of ESR ingot Ignition technique figure.
Fig. 3 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, during hammer cogging Heating artwork.
Fig. 4 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, the annealing of steel billet Artwork.
Fig. 5 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, the quenched heat of round steel The quenching technical figure processed.
Fig. 6 is in the preparation method of nuclear power station CRDM detachable fitting of the present invention, the quenched heat of round steel The tempering process figure processed.
Fig. 7 is the sample that the preparation method according to nuclear power station CRDM detachable fitting of the present invention obtains Non-metallic inclusion shape appearance figure.
Embodiment
In order to make the goal of the invention of the present invention, technical scheme and technique effect thereof become apparent from, below in conjunction with attached Figure and embodiment, the present invention is described in more detail.It should be appreciated that the reality described in this specification Execute example merely to explain the present invention, be not intended to limit the present invention.
The main technique of the preparation method of nuclear power station CRDM detachable fitting of the present invention includes: vacuum Smelting → casting electrode → electroslag remelting → ESR ingot annealing → hammer cogging → annealing billet → hot rolled circular steel → Round steel Tempering and Quenching → performance detection → ultrasonic examination → inspection warehouse-in
1. vacuum metling
Picking of raw material crome metal, manganese metal, metallic nickel, metal molybdenum, pure iron, electrode carbon and silicon metal, sternly Lattice control according to the subject component shown in table 1 and adjust the composition of steel, it is ensured that impurity element and remnants in raw material Constituent content meets the requirements.Before charging, nickel and pure iron are all through processing of rust removing;Before steel-making, check vacuum drying oven and Furnace lining is in shape, and the constituent content such as on-the-spot sample analysis C, Cr, Ni, Mn, Si, Al, by table 1 institute Show that target call adjusts.
The essential element of table 1 steel and weight percentage thereof
Refer to artwork shown in Fig. 1, the concrete technology of vacuum metling includes:
1) vacuum chamber is opened, at loading alloy material in addition to metal Mn in vaccum sensitive stove, in auto feed Room loads metal Mn;
2) closing vacuum chamber, vacuum must reach 2.7x10-2mbar;
3) vacuum metling:
0~1 hour: starting steel-making, beginning to warm up power is 150kw, and during heating, power takes segmentation to promote;
1~3.5 hour: heating power rises to 200~250kw;
3.5~4 hours: smelt, 3.5 little started melting down (alloy melting) constantly, and 4 little the most melting down are carried out Stokehold sample analysis;
Carrying out stokehold sample analysis after 4~5.5 hours: 4 hours, 5.5 little evacuation the most again keep vacuum to reach 2.7x10-2mbr;
5.5~6 hours: refine, temperature must reach > 1500 DEG C, and now heating power can be down to 120kw;
6~8 hours: applying argon gas carries out argon atmosphere smelting, its pressure was 6666Pa;
8~10 hours: 8 little constantly, auto feed room adds metal Mn (early add Mn can volatilize) in stove. Power ascension is smelted to 200~250kw, and the 10 little finished product samples that take constantly carry out on-the-spot sample analysis C, Cr, Ni, Mn, The elements such as Si, Al, as shown in table 1, target call adjusts;
2. casting electrode: with continued reference to artwork shown in Fig. 1,12~15 little carry out finished product smelting constantly, and 15 Charged casting during hour liquid steel temperature > 1500 DEG C, the molten steel of casting forms electroslag remelting electrode bar.During cast, Control poring rate, it is ensured that have enough molten steel feeding, prevent shrinkage cavity and being involved in property to be mingled with, allow simultaneously and be mingled with Fully float, wherein, the demoulding time: >=1 hour;Casting electrode: Φ 290mmx1800mm.
3. electroslag remelting: in order to improve metallurgical quality, carries out electroslag remelting secondary smelting by the electrode bar of cast, With the degree of purity of raising steel, reduce the field trash in steel, reduce the size of field trash and change dividing of field trash Cloth.
Electroslag remelting specifically comprises the processes of: use the melt cinder starting the arc, wherein, electrode: φ 290mmx1800mm; Crystallizer: φ 352/ φ 400x2400mm;Slag system: CaF2:Al2O3;Dummy plate: general steel grade;Startup plate: General steel grade.
4. ESR ingot annealing: after electroslag remelting, ESR ingot is annealed, annealing process figure as shown in Figure 2: Be incubated about 3 hours at≤600 DEG C, be heated to the firing rate of≤120 DEG C/h 840 DEG C;> 840 DEG C protect After temperature about 6 hours, cool down with the rate of cooling of≤50 DEG C/h.After annealing, at the head 50mm of ESR ingot Use drilling machine to take brill sample at place, afterbody 100mm and carry out chemical analysis, to guarantee that the alloying component of ESR ingot is Subject component shown in table 2.
The essential element of table 2 ESR ingot and weight percentage thereof
5. hammer cogging: ESR ingot uses 3 tons of Single arm to carry out hammer cogging after heating in batch-type furnace, adds Thermal process figure is as it is shown on figure 3, particularly as follows: ESR ingot is after≤600 DEG C of insulations about 3 hours, with≤120 DEG C/h Firing rate be heated to > 1100 DEG C, and > 1100 DEG C of insulations 6 hours.
Hammer cogging specification: 120x120x3100~4000mm (forging ratio: > 7);
Open forging temperature >=1070 DEG C, stop forging temperature >=900 DEG C;
During forging steel billet temperature to 900 DEG C time melt down, melt down temperature: 1180 DEG C ± 10 DEG C, melt down temperature retention time: >=1.00 hours;
Forging mode: 3~5 fire time produce.
Final forging temperature: >=850 DEG C;
Additionally, during steel ingot cogging, excise head, tail, resection rate should ensure that: head resection rate >=8%;Afterbody Resection rate >=3%.
6. annealing billet: after steel ingot hammer cogging, steel billet heat send annealing, the artwork of annealing billet such as Fig. 4 institute Show, particularly as follows: at 600~650 DEG C after material a period of time (time is not particularly limited), with≤120 DEG C/h Firing rate be heated to 860 DEG C ± 10 DEG C;After 860 DEG C ± 10 DEG C insulations 5~6 hours, with 20~40 DEG C/h Rate of cooling be cooled to 400 DEG C and come out of the stove;Check field trash after steel billet cooling and carry out ultrasonic inspection flaw detection, Surface defect, billet specification: 120x120x3100~4000mm are removed in the full peeling in qualified rear surface, finishing.
7. hot rolled circular steel: hot rolled circular steel produces at high alloy and carries out on line (Continuous mill train), and hot rolling blank dimension is: φ 50mm, heating technological specification is as shown in table 3.
Table 3 hot rolled circular steel heating technological specification
Concrete, rolling technological parameter is as follows:
Rolling specs: φ 50mm, finished product rolling addition 1mm;
Continuous tunnel furnace design temperature: 1050 DEG C~1150 DEG C;
Tandem rolling inlet temperature: 900 DEG C~1050 DEG C;
Finishing temperature: >=900 DEG C;
8 (length about 4~5 meters) it are cut into after hot rolling;
Cooling: enter to move cover stove preannealing;
Finishing requires: diameter and profile tolerance are specified by standard;
Finishing route is: aligning → ultrasonic examination → finishing (sand stripping) → test package;
Hot-rolled finished product weight: 584 kilograms.
8. round steel Tempering and Quenching:
The quenching technical figure of round steel Tempering and Quenching is as shown in Figure 5: be incubated about 0.5 hour at≤650 DEG C, so Post-heating 4~be warming up to 960~1000 DEG C in 5 hours;After 960~1000 DEG C of insulations 1~1.2 hour, oil quenching;
The tempering process figure of round steel Tempering and Quenching is as shown in Figure 6: be incubated about 0.5 hour at≤550 DEG C, so Post-heating 1.5~be warming up to 660~680 DEG C in 2 hours;After 660~680 DEG C of insulations 3~3.5 hours, air cooling.
After adjusting heat treatment, in addition it is also necessary to carry out performance detection and ultrasonic examination, satisfactory product inspection Warehouse-in.
Experiment detection
The examination of nonmetallic inclusion
The examination of nonmetallic inclusion is carried out: take at detachable fitting blank 1/2 radius vertical by GB/T10561-2005 After cross-section samples grinds polishing, check non-metallic inclusion, non-metallic inclusion pattern such as Fig. 7 under the microscope Shown in, assay such as table 4.
Table 4 examination of nonmetallic inclusion result
Tension test
Carried out tensile test at room temperature by GB/T228.1-2010, carried out 350 DEG C of high temperature by GB/T4338-2006 Tension test: take hoop tensile sample 6 in detachable fitting blank 1/2 radial position, carry out room temperature and 350 DEG C of high temperature tension tests, sample working portion a diameter of Φ 10mm, stretch test result such as table 5.
Table 5 stretch test result
Low-temperature impact test
Low-temperature impact test is carried out: take ring in detachable fitting blank 1/2 radial position by GB/T229-2007 To impact specimen 3, carrying out 0 DEG C of low-temperature impact test, sample uses 10mmx10mmx55mm standard V Type notched specimen, breach axis is perpendicular to blank outer surface, and Impulse Test Result is shown in Table 6.
Table 6 low-temperature impact test result
Hardness test
Hardness test is carried out: cross-section carries out Bu Shi at detachable fitting blank two ends by GB/T231.1-2009 Hardness test, each end face uniformly surveys the hardness number of 3, and test result is shown in Table 7.
Table 7 Brinell hardness test result
In conjunction with above detailed description and practice examining, nuclear power station CRDM detachable fitting of the present invention And preparation method thereof have following technical effect that
1. by optimizing chemical analysis and technique, CRDM detachable fitting under conditions of use can safe operation, During the clutch partially-working of end in elastic range, plastic deformation not occurring, the life-span meets setting of CRDM Meter specification and national standard requirement, it is achieved that the production domesticization that CRDM detachable fitting manufactures.
2., when being arranged in CRDM operation, safe and reliable, the especially clutch configuration of end has sufficiently Elastic.
3. can utilize domestic existing process equipment processing and manufacturing, there is no technologic difficulty, be beneficial to batch raw Produce, accelerate localization process.
The announcement of book and teaching according to the above description, those skilled in the art in the invention can also be to above-mentioned Embodiment carries out suitable change and amendment.Therefore, the invention is not limited in disclosed and described above Some modifications and changes of the present invention be should also be as falling into the guarantor of the claim of the present invention by detailed description of the invention In the range of protecting.Although additionally, employ some specific terms in this specification, but these terms are simply Facilitate explanation, the present invention is not constituted any restriction.

Claims (8)

1. the preparation method of a nuclear power station CRDM detachable fitting, it is characterised in that include with Lower step:
1) raw material vacuum metling are chosen, it is thus achieved that molten steel;
2) pouring molten steel electrode is used;
3) electrode electroslag remelting being obtained ESR ingot, wherein, by weight percentage, ESR ingot contains 0.080-0.140%C ,≤0.50%Si ,≤0.80%Mn ,≤0.020%S ,≤0.030%P, 0.50-1.00%Ni, 11.50-13.00%Cr ,≤0.10%Co ,≤0.050%Al ,≤0.60%Mo and surplus Fe;
4) hammer cogging after ESR ingot being made annealing treatment;
5) after annealing billet processes, after hot rolled round steel, round steel Tempering and Quenching and ultrasonic inspection obtain nuclear power Stand CRDM detachable fitting;The annealing process of steel billet is: at 600~650 DEG C after expecting, with≤ The firing rate of 120 DEG C/h is heated to 860 DEG C ± 10 DEG C;After 860 DEG C ± 10 DEG C insulations 5~6 hours, with The rate of cooling of 20~40 DEG C/h is cooled to 400 DEG C and comes out of the stove.
Preparation method the most according to claim 1, it is characterised in that step 1) in, during vacuum metling Vacuum reach 2.7x10-2Mbar, and first at loading alloy material in addition to metal Mn in vaccum sensitive stove, Metal Mn is added by auto feed room after being filled with argon.
Preparation method the most according to claim 1, it is characterised in that step 1) in, each element uses Pure material is allocated into.
Preparation method the most according to claim 1, it is characterised in that step 4) in, moving back of ESR ingot Ignition technique is: is incubated 3 hours at≤600 DEG C, is heated to the firing rate of≤120 DEG C/h > 840 DEG C; > after 840 DEG C of insulations 6 hours, cool down with the rate of cooling of≤50 DEG C/h.
Preparation method the most according to claim 1, it is characterised in that step 4) in, the forging of ESR ingot Heating technique when making cogging is: by ESR ingot after≤600 DEG C of insulations 3 hours, with adding of≤120 DEG C/h Thermal velocity is heated to > 1100 DEG C and > 1100 DEG C of insulations 6 hours.
Preparation method the most according to claim 1, it is characterised in that step 5) in, the quenched heat of round steel Processing specifically comprises the processes of: quenching, be incubated 0.5 hour at≤650 DEG C, then heating is warming up to for 4~5 hours 960~1000 DEG C;After 960~1000 DEG C of insulations 1~1.2 hour, oil quenching;Tempering, is incubated 0.5 at≤650 DEG C Hour, then heating is warming up to 660~680 DEG C in 1.5~2 hours;After 660~680 DEG C of insulations 3~3.5 hours, Air cooling.
Preparation method the most according to claim 1, it is characterised in that step 4) in ESR ingot annealing After process, sampling confirms that the alloying component of ESR ingot and content are step 3) in alloying component and content.
8. a nuclear power station CRDM detachable fitting, it is characterised in that by weight percentage, Described nuclear power station CRDM detachable fitting containing 0.080-0.140%C ,≤0.50%Si ,≤0.80%Mn, ≤ 0.020%S ,≤0.030%P, 0.50-1.00%Ni, 11.50-13.00%Cr ,≤0.10%Co ,≤0.050%Al, ≤ 0.60%Mo and surplus Fe, it is to be obtained by the preparation method according to any one of claim 1-7.
CN201410062565.2A 2014-02-24 Nuclear power station CRDM detachable fitting and preparation method thereof Active CN103820728B (en)

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Application Number Priority Date Filing Date Title
CN201410062565.2A CN103820728B (en) 2014-02-24 Nuclear power station CRDM detachable fitting and preparation method thereof

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Application Number Priority Date Filing Date Title
CN201410062565.2A CN103820728B (en) 2014-02-24 Nuclear power station CRDM detachable fitting and preparation method thereof

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CN103820728B true CN103820728B (en) 2016-11-30

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Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101812624A (en) * 2010-04-21 2010-08-25 中国科学院金属研究所 Preparation of 1 Cr (Chromium) 13 thick wall tubular products of control rod of nuclear reactor control bar drive mechanism

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101812624A (en) * 2010-04-21 2010-08-25 中国科学院金属研究所 Preparation of 1 Cr (Chromium) 13 thick wall tubular products of control rod of nuclear reactor control bar drive mechanism

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