CN102703828A - Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof - Google Patents
Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof Download PDFInfo
- Publication number
- CN102703828A CN102703828A CN2012101470128A CN201210147012A CN102703828A CN 102703828 A CN102703828 A CN 102703828A CN 2012101470128 A CN2012101470128 A CN 2012101470128A CN 201210147012 A CN201210147012 A CN 201210147012A CN 102703828 A CN102703828 A CN 102703828A
- Authority
- CN
- China
- Prior art keywords
- strip material
- preparation
- nuclear power
- antidetonation
- annealing
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Abstract
The invention discloses a novel shockproof strip material of a steam generator of a nuclear power station and a preparation method thereof. The material comprises the following components by weight: 0.01-0.08% of C, 0.10-1.0% of Si, 0.10-1.0% of Mn, less than 0.040% of P, less than 0.030% of S, 11.5-14.5% of Cr, 0.05-0.6% of Ni, 0.05-0.30% of Al, 0.01-1.0% of Re and the balance, Fe and unavoidable impurities. The preparation method includes A. conducting raw material preparation according to the weight percentage of the components of the shockproof strip material; B. cleaning and drying the surface of the raw materials according to the proportion, filling the materials in the smelting sequence into a vacuum smelting furnace for high vacuum smelting and adding the rare earth Re into the vacuum smelting process; C. conducting electroslag refining, D. conducting forging, E. conducting hot rolling, F. conducting annealing and G. conducting multiple drawing, annealing and drawing to obtain a shockproof strip material product. The material has the advantages of being reasonable in component design, low in cost, stable in preparation process, excellent in corrosion resistance, fatigue resistance, creep resistance and processability and safe and reliable in use.
Description
Technical field
The present invention relates to a kind of novel Nuclear power plants steam generator antidetonation strip material and preparation method thereof.
Background technology
AP1000 is the third generation million kilowatt advanced pressurized water reactor nuclear power generating sets of US Westinghouse company's exploitation.AP1000 is different from the security system that the principal feature that two generations added CPR1000 compressed water reactor nuclear power unit is exactly " non-active "." non-active " design concept utilizes the inherent hot-working hydraulic characteristic exactly; Simplify the design of security system; Make Nuclear power plants guarantee that the measure of safety no longer relies on the operation of active equipment such as pump, blower fan, thereby reduced valve, pump, cable and the antidetonation factory building of security level significantly; Cancelled 1E level emergency diesel dynamo system; Reduced the active equipment of most of security level; Reduced large material usage; System simplification makes design simplification, processing set-up simplification, construction volume minimizing, operation and the also corresponding minimizing of maintenance capacity.Non-active major accident prevention and the mitigation strategy that adopt in the design are improved safety performance; While has also improved unit and economy energy industry is the basis of national economy; Be the important step of restriction national economy sustained and rapid development, along with development and national economy, people are increasingly high to standard of living and environmental protection requirement; Therefore, greatly develop the dominant direction that the nuclear power cause has become current energy development.It is conspicuous that nuclear power is compared its advantage with thermal power generation and other new forms of energy.Vapour generator is the hinge of pressurized-water reactor nuclear power plant one loop and secondary circuit, is the barrier of cutting apart the medium of a loop and secondary circuit, is one of Nuclear power plants key equipment.A Nuclear power plants need be provided with several vapour generators, includes ten hundreds of heat-transfer pipes, and the high-temperature setting-out flows in tube bank, supplies with water and flows with vertical direction along pipe; Be heated simultaneously, be vaporized then, steam gets into the steam turbine generating; Can cause vibrations with these pipe fluid in contact, break, directly cause vapour generator and damage because of vibrations can cause damaged tubular; Change a vapour generator and need several hundred million dollars of expenses, need the shutdown some months, cause great financial loss.For effectively preventing pipe vibrations, be provided with shockproof the nuclear plant safety reliability service played keying action.。The anti-bar of nuclear power evaporator is to be used for fixing vaporizer key part U type pipe, owing to be work under the environment of HTHP and vibration, the therefore strictness suitable to the requirement of material. hereThe present main dependence on import of this type of critical material.
Vapour generator antidetonation bar is under high temperature, high pressure, strong corrosive environment, to use, and high temperature strength, erosion resistance, antifatigue, creep resistance and the workability of making the antidetonation strip material proposed strict demand.China is used to make still dependence on import of antidetonation strip material at present; Therefore research and develop and make antidetonation strip material with superior corrosion resistance, antifatigue, creep resistance and workability; Substituting import, the economy and the safe reliability of effective raising Nuclear power plants had crucial meaning.
Summary of the invention
The objective of the invention is to overcome the deficiency in the existing anti-strip material technology, novel nuclear power station steam generator antidetonation strip material and preparation method thereof is provided.A kind of novel nuclear power station steam generator antidetonation strip material of the present invention and preparation method thereof, material price is low, design of components is reasonable, ME is simple, has superior corrosion resistance, antifatigue, creep resistance and processability.Said novel nuclear power station steam generator antidetonation strip material method tensile strength can reach 520MPa, and ys can reach 345MPa, and elongation is greater than 20%, and hardness is less than 195.
To achieve these goals, the present invention realizes through following technical scheme: a kind of novel nuclear power station steam generator antidetonation strip material, to count by weight percentage, and ingredient is following:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities; The purity of wherein said Si, Mn, Cr, Ni, Ti, Fe is greater than 99%; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
Said a kind of novel nuclear power station steam generator antidetonation strip material preparation method comprises the steps:
A, calculate by the weight percent meter of antidetonation strip material ingredient and to carry out preparation of raw material:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities;
B, will be by after the clean dry of the raw material of aforementioned preparation surface, pack into by the melting order and to carry out high vacuum in the vacuum smelting furnace and smelt, its middle-weight rare earths Re adds in the vacuum metling process, 1550 ℃～1620 ℃ of said refining temperatures, refining time 20～27 minutes;
C, electroslag refining; 1550 ℃～1620 ℃ of refining temperatures, melting voltage: 45/50V; Melting electric current: 2600/3000A;
D, forging are opened and are forged 1160 ℃ of temperature, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=900 ℃;
F, annealing, 788 ℃～815 ℃ of annealing temperatures;
G, carry out the drawing → annealing → drawing of multi-pass, obtain the Shockproof strip material finished product, said drawing adopts bicycle to carry out, and wherein said annealing temperature is 788 ℃～815 ℃.
Preparing method's major technique characteristics of the present invention are: adopt vacuum refining furnace to smelt, make the degassing fully, again through electroslag refining; Make molten steel clean, rare earth Re adds further raising antidetonation strip material quality and mechanical property, the process annealing of drawing process in the vacuum metling process; Drawing adopts bicycle to carry out at a slow speed; The heat accumulation that is produced when reducing friction finally obtains tensile strength and can reach 520MPa, and ys can reach 345MPa; Elongation is greater than 20%, and hardness is less than 195 antidetonation strip material.
The principle of a kind of novel nuclear power station steam generator antidetonation composition that strip material designs according to the invention is following:
C: very effective sclerosis and solution strengthening constituent element, stablize martensitic structure, proof strength.But usually occur as formation of crack, form crisp sclerous tissues easily and cause delayed cracking like too high levels, its composition weight % is limited in 0.01-0.08%;
Mn: deoxidation and desulfidation, guarantee the important element of oxidation-resistance, less than 0.01% can not obtain abundant deoxidation, surpasses 1.5% intensity and reduces, and its composition weight % is limited in 0.10-1.0%;
Si: deoxidation, raising ys, high-temperature corrosion resistance property, less than 0.01% can not obtain abundant oxidation-resistance, surpasses 0.90% toughness and reduces, and its composition weight % is limited in 0.2-1.0%;
Ni: improve toughness of material, the raising of intensity is also had contribution, its composition weight % is limited in 0.05-0.6%;
Cr: guarantee oxidation-resistance, high-temperature corrosion resistance property, improve the indispensable element of hot strength, content is low excessively, can not manifest effect, too high levels, and intensity and toughness significantly reduce, and its composition weight % is limited in 11.5-14.5%;
S, P: be inevitable detrimental impurity element in the material, its content is low more good more, its composition weight %, and P :≤0.040%, S :≤0.030%;
Re: add rare earth in the material, and have good oxidation-resistance under the compound action of Cr, Si, rare earth is the strong reducing property element; Rare earth and sulphur have very big avidity, in bath, not only have desoxydatoin, also have size, form and distribution effect that obvious desulfurization improves sulfide inclusion; Reduce the inclusion content in the material; Can change composition, form, distribution and the character of inclusion, suppress the segregation of these inclusiones in crystal boundary, thereby improve the various performances of material; Like toughness, weldableness, composition weight % is limited in 0.01-1.0% among the present invention.
The employing a kind of novel nuclear power station steam generator antidetonation strip material that the present invention designed compared with prior art has following advantage:
1. composition is reasonable in design, cost is low, safe and reliable;
2. its tensile strength of this antidetonation strip material can reach 520MPa, and ys can reach 345 MPa, and elongation is greater than 20%, and hardness is less than 195, and long term operation has higher-strength and corrosion resistance under 600 ℃ of high temperature, its high temperature stress intensity stabilization;
3. again because of having added micro-REE and having adopted special preparation technology, guarantee that material has superior corrosion resistance, antifatigue, creep resistance and processability;
4. a kind of novel nuclear power station steam generator antidetonation strip material of the present invention is guaranteed the safe reliability that the antidetonation bar uses, and effectively prolongs the work-ing life of nuclear power station steam generator, reduces cost, and significantly improves economic benefit.
Embodiment
In order to deepen to understanding of the present invention, will combine embodiment that the present invention is made further detailed description below, following examples only are used to explain the present invention, do not constitute the qualification to protection domain of the present invention.
A kind of novel nuclear power station steam generator antidetonation strip material of the present invention is counted by weight percentage, and ingredient is following:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities; The purity of wherein said Si, Mn, Cr, Ni, Ti, Fe is greater than 99%; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
Said a kind of novel nuclear power station steam generator antidetonation strip material preparation method comprises the steps:
A, calculate by the weight percent meter of antidetonation strip material ingredient and to carry out preparation of raw material:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities;
B, will be by after the clean dry of the raw material of aforementioned preparation surface, pack into by the melting order and to carry out high vacuum in the vacuum smelting furnace and smelt, its middle-weight rare earths Re adds in the vacuum metling process, 1550 ℃～1620 ℃ of said refining temperatures, refining time 20～27 minutes;
C, electroslag refining; 1550 ℃～1620 ℃ of refining temperatures, melting voltage: 45/50V; Melting electric current: 2600/3000A;
D, forging are opened and are forged 1160 ℃ of temperature, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=900 ℃;
F, annealing, 788 ℃～815 ℃ of annealing temperatures;
G, carry out the drawing → annealing → drawing of multi-pass, obtain the Shockproof strip material finished product, said drawing adopts bicycle to carry out, and wherein said annealing temperature is 788 ℃～815 ℃.
A kind of novel nuclear power station steam generator antidetonation strip material preparation through heat (batch) number is: 125-0122,0123,0124,0125,0126,0127,0128,0129 implements.
Embodiment 1-8 stove antidetonation strip material ingredient and content % by weight calculate, respectively as follows:
First stove: C:0.02%; Si:0.45%; Mn:0.81%; P:0.010%; S:0.005%; Cr:12.0%; Ni:0.20%; AL:0.25%; Re:0.10%;
Second stove: C:0.03%; Si:0.40%; Mn:0.80%; P:0.012%; S:0.009%; Cr:12.5%; Ni:0.18%; AL:0.22%; Re:0.09%;
The 3rd stove: C:0.035%; Si:0.35%; Mn:0.85%; P:0.010%; S:0.008%; Cr:12.2%; Ni:0.25%; AL:0.20%; Re:0.08%;
The 4th stove: C:0.045%; Si:0.42%; Mn:0.87%; P:0.011%; S:0.007%; Cr:12.8%; Ni:0.15%; AL:0.17%; Re:0.09%;
The 6th stove: C:0.042%; Si:0.41%; Mn:0.75%; P:0.015%; S:0.010%; Cr:12.3%; Ni:0.18%; AL:0.22%; Re:0.09%;
The 7th stove: C:0.058%; Si:0.35%; Mn:0.85%; P:0.010%; S:0.008%; Cr:12.2%; Ni:0.12%; AL:0.18%; Re:0.08%;
The 8th stove: C:0.051%; Si:0.33%; Mn:0.74%; P:0.012%; S:0.006%; Cr:12.9%; Ni:0.11%; AL:0.21%; Re:0.06%;
Above-mentioned eight stove embodiment its preparation methods are: all select pure iron for use, according to the present invention's eight stove embodiment design mix batching, vacuum refining furnace is smelted; 1550 ℃～1620 ℃ of refining temperatures; 27 minutes → electroslag refining of refining time,, 1550 ℃～1620 ℃ of refining temperatures, melting voltage: 45/50V; The melting electric current: 2600/3000A → forging, open and forge 1150 ℃ of temperature, final forging temperature >=900 ℃ → hot rolling; 1150 ℃ of hot-rolled temperatures, finishing temperature >=900 ℃ → vacuum annealing thermal treatment; 788 ℃～815 ℃ of annealing temperatures, 4.5 hours → multi-pass of soaking time drawing-annealing-drawing, the process annealing temperature adopts 788 ℃～815 ℃ annealing; Drawing is adopted bicycle at a slow speed; Speed is 10 meters/minute carries out, according to customer need, and drawing passes ф 16-14.5*14-11*13.5-9*13-7*13-5*12.5-4.4*12.5.
Above embodiment design the preparation a kind of novel nuclear power station steam generator antidetonation strip material relevant department its composition, comprehensive mechanical property have been carried out detection, test, examining report is following:
One. mechanical industry quality of materials inspection center
The material classification: the antidetonation bar,
Sample title: present embodiment antidetonation strip material; Sample characteristic: piece appearance
Detect foundation and/judgment basis: ISO 15350:2000 GB/T 11170-2008 ASTME1019-2008
Detect data/result: qualified
C：0.045%；Si：0.42%?；Mn：0.87%；P：0.011%；S：0.006%；Cr：12.85%；Ni：0.16%；AL：0.17%;?Re：0.05%
Two. quality physical and chemical measuring room
Material classification: antidetonation bar
Sample title: present embodiment antidetonation strip material
Embodiment 1-8 stove, 1 in every stove, annealing, specification: ф 10mm
Test basis: DF-SG/PS-011 Rev:A; NPS-DSD-SGO22 Rev:A;
Technical qualification: NPS-DSD-SGOZZ
Test temperature: room temperature
1. mechanical property test
2. metallographic examination
3. novel nuclear power station steam generator antidetonation strip material test evaluation report
1). test specimen state: before shockproof the assembling
2). check type: chemical analysis, mechanical property, UT, thermal treatment, visual inspection, dimension inspection.
Assay:
1. visual inspection, dimension inspection, angle and planeness inspection.Result: qualified.
2. heat analysis
1). UT (hot rolling bleaching back).Result: zero defect.
2). thermal treatment.Result: qualified.
3. mechanical property check and analysis.Result: qualified.
4. product analysis.Result: qualified.
Evaluation result: according to antidetonation bar trial-production part evaluation situation analysis, present embodiment third generation nuclear power AP1000 steam generator antidetonation strip material satisfies each item requirement of vapour generator with the antidetonation bar, and manufacturing process and product is stable.
Detect through above embodiment and mechanical property; A kind of novel nuclear power station steam generator antidetonation strip material that the present invention designed has that composition is reasonable in design, cost is low, stable manufacturing process; Have superior corrosion resistance, antifatigue, creep resistance and processability; Satisfy each item request for utilization of vapour generator, guarantee safe and reliable with the antidetonation bar.To enhancing productivity, effectively prolong the work-ing life of nuclear power station steam generator, be the nuclear power domestic manufacture of key equipment, reducing production costs has crucial economic implications.
Claims (2)
1. novel nuclear power station steam generator antidetonation strip material, it is characterized in that: count by weight percentage, ingredient is following:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities; The purity of wherein said Si, Mn, Cr, Ni, Ti, Fe is greater than 99%; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
2. a novel nuclear power station steam generator antidetonation strip material preparation method is characterized in that: comprise the steps:
A, calculate by the weight percent meter of antidetonation strip material ingredient and to carry out preparation of raw material:
C：0.01-0.08%； Si：0.10-1.0%?； Mn：0.10-1.0%；
P：≤0.040%； S：?≤0.030%； Cr：11.5-14.5%；
Ni：0.05-0.6%； AL：0.05-0.30%; ?Re：0.01-1.0%;
Surplus is Fe and unavoidable impurities;
B, will be by after the clean dry of the raw material of aforementioned preparation surface, pack into by the melting order and to carry out high vacuum in the vacuum smelting furnace and smelt, its middle-weight rare earths Re adds in the vacuum metling process, 1550 ℃～1620 ℃ of said refining temperatures, refining time 20～27 minutes;
C, electroslag refining; 1550 ℃～1620 ℃ of refining temperatures, melting voltage: 45/50V; Melting electric current: 2600/3000A;
D, forging are opened and are forged 1160 ℃ of temperature, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=900 ℃;
F, annealing, 788 ℃～815 ℃ of annealing temperatures;
G, carry out the drawing → annealing → drawing of multi-pass, obtain the Shockproof strip material finished product, said drawing adopts bicycle to carry out, and wherein said annealing temperature is 788 ℃～815 ℃.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012101470128A CN102703828A (en) | 2012-05-14 | 2012-05-14 | Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012101470128A CN102703828A (en) | 2012-05-14 | 2012-05-14 | Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102703828A true CN102703828A (en) | 2012-10-03 |
Family
ID=46896872
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012101470128A Pending CN102703828A (en) | 2012-05-14 | 2012-05-14 | Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102703828A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107345288A (en) * | 2017-06-29 | 2017-11-14 | 张家港海锅新能源装备股份有限公司 | A kind of manufacture method of nuclear power generating equipment steel and its forging |
| CN116136011A (en) * | 2021-11-17 | 2023-05-19 | 江苏新华合金有限公司 | 12Cr13 bar for evaporator pull rod and pull rod nut and preparation method thereof |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02175842A (en) * | 1988-12-28 | 1990-07-09 | Hitachi Ltd | Stainless steel for unclear reactor core equipment and its production |
| JP2007162112A (en) * | 2005-12-16 | 2007-06-28 | Sumitomo Metal Ind Ltd | Martensitic iron based heat resistant alloy |
| CN100999806A (en) * | 2006-12-31 | 2007-07-18 | 许季祥 | High performance corrosion-proof rare earth super strength dual-phase stainless steel and its smelting tech. |
| CN101831592A (en) * | 2010-05-27 | 2010-09-15 | 江苏新华合金电器有限公司 | Shockproof strip material of nuclear power station steam generator, and preparation method thereof |
-
2012
- 2012-05-14 CN CN2012101470128A patent/CN102703828A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02175842A (en) * | 1988-12-28 | 1990-07-09 | Hitachi Ltd | Stainless steel for unclear reactor core equipment and its production |
| JP2007162112A (en) * | 2005-12-16 | 2007-06-28 | Sumitomo Metal Ind Ltd | Martensitic iron based heat resistant alloy |
| CN100999806A (en) * | 2006-12-31 | 2007-07-18 | 许季祥 | High performance corrosion-proof rare earth super strength dual-phase stainless steel and its smelting tech. |
| CN101831592A (en) * | 2010-05-27 | 2010-09-15 | 江苏新华合金电器有限公司 | Shockproof strip material of nuclear power station steam generator, and preparation method thereof |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107345288A (en) * | 2017-06-29 | 2017-11-14 | 张家港海锅新能源装备股份有限公司 | A kind of manufacture method of nuclear power generating equipment steel and its forging |
| CN107345288B (en) * | 2017-06-29 | 2018-09-18 | 张家港海锅新能源装备股份有限公司 | A kind of manufacturing method of nuclear power generating equipment steel and its forging |
| CN116136011A (en) * | 2021-11-17 | 2023-05-19 | 江苏新华合金有限公司 | 12Cr13 bar for evaporator pull rod and pull rod nut and preparation method thereof |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101831592B (en) | Shockproof strip material of nuclear power station steam generator, and preparation method thereof | |
| CN102732751B (en) | Anti-vibration alloy material for nuclear power station steam generator and preparation process thereof | |
| CN101851714A (en) | Shockproof strip end-plate material of vapor generator of nuclear power plant and preparation method thereof | |
| CN102732801B (en) | Pull rod material for nuclear power station steam generator and preparation process thereof | |
| CN101314202B (en) | Method for producing wind-electricity principal axis by gathering stock full fibre upset forging | |
| CN103409699B (en) | Steel forging with ultra-high strength and ultra-high low-temperature impact on box body of fracturing pump valve and manufacturing method of steel forging | |
| CN108220783A (en) | A kind of austenite heat-resistance stainless steel and its manufacturing method | |
| EP2377962B1 (en) | Precipitation hardenable martensitic stainless steel and steam turbine blade using the same | |
| CN102345077B (en) | Large-expansion-ratio expansion pipe steel with high product of strength and elongation and preparation method thereof | |
| CN107619994A (en) | A kind of anti-CO2/H2S and sulfate reducing bacteria corrosion seamless line pipe and its manufacture method | |
| CN102181752A (en) | Hand hole sealing cover spring material for steam generator of nuclear power plant and preparation method of hand hole sealing cover spring material | |
| CN101921967A (en) | Novel austenitic heat-resistance stainless steel | |
| CN100370049C (en) | Ferritic stainless steel having high temperature creep resistance | |
| CN103952633A (en) | high-strength steel wire rod with good low temperature impact toughness and production method thereof | |
| CN103498072A (en) | High-strength high-impact-toughness titanium alloy used for oil well and gas well, and preparation method thereof | |
| CN103045970A (en) | Extra-thick hydrogen present 15CrMoR steel plate and production method thereof | |
| CN103695806B (en) | A kind of austenitic heat-resistance steel | |
| CN102703828A (en) | Novel shockproof strip material of steam generator of nuclear power station and preparation method thereof | |
| CN102162063A (en) | Ferritic stainless steel medium plate and manufacturing method thereof | |
| CN102286700B (en) | Sulfuric-acid-resistant dew point corrosion steel with tensile strength greater than or equal to 800Mpa grade and preparation method thereof | |
| CN103498079A (en) | Antioxidative iron-nickel-based alloy | |
| CN101906593A (en) | Intercrystalline corrosion-free high temperature and pressure boiler steel pipe and manufacturing method thereof | |
| CN102586676A (en) | Rare earth-containing high-strength steel plate for manufacturing wind power tower, and rolling method of steel plate | |
| CN103725981A (en) | Preparation method of high-performance magnetic control connecting piece | |
| CN103725991A (en) | Manufacturing method of magnetic control connecting piece for pressurized water reactor nuclear island |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C53 | Correction of patent of invention or patent application | ||
| CB02 | Change of applicant information |
Address after: 225722 No. 19, Zhang Guo, South Town, Jiangsu, Xinghua Applicant after: Jiangsu Xinhua Alloy Electric Apparatus Co., Ltd. Address before: 225722 No. 19, Zhang Guo, South Town, Jiangsu, Taizhou Applicant before: Jiangsu Xinhua Alloy Electric Apparatus Co., Ltd. |
|
| C12 | Rejection of a patent application after its publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20121003 |