CN102732801A - Pull rod material for nuclear power station steam generator and preparation process thereof - Google Patents
Pull rod material for nuclear power station steam generator and preparation process thereof Download PDFInfo
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Abstract
The invention discloses a pull rod material for a nuclear power station steam generator. The pull rod material comprises the following components by weight percent: C 0.080 to 0.015%, Si 0.10 to 1.0%, Mn 0.4 to 1.0%, P <= 0.030%, S <= 0.030%, Cr 11.5 to 13.5%, Ni 0.01 to 0.50% and Re 0.02 to 0.80%, with the balance being Fe and unavoidable impurities. A preparation process for the pull rod material comprises the following steps: A, preparation of raw materials according to weight percent of the components of the pull rod material; B, smelting of the raw materials in an induction furnace according to a melting order, wherein the misch metal Re is added into molten steel within 2 to 3 min before steel tapping during smelting in the induction furnace, tapping is carried out immediately after the misch metal Re is added and an argon shield method is adopted for casting during tapping; C, re-melting of electroslag; D, forging; E, hot rolling; F, quenching; and G, tempering. A finished product of the connecting pull rod material is obtained after the above-mentioned steps. According to the invention, the advantages of reasonable design of the components and low cost are achieved and the service life of the nuclear power station steam generator is effectively prolonged.
Description
Technical field
The nuclear power station steam generator that the present invention relates to a kind of new material technology field is mainly used in pressurized-water reactor nuclear island vapour generator and uses rod material with rod material and preparation method thereof.
Background technology
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.The main effect of vapour generator is a water of the heat of water in the loop being passed to secondary circuit, makes its vaporization.Owing to loop current have radioactivity through reactor core, thus vapour generator and pressurized vessel and a return common constitute prevent the second road barrier that radioactivity is excessive.When PWR nuclear power plant normally moved, secondary circuit should not receive the pollution of a loop water, be do not have radioactive.The PWR nuclear power plant vapour generator in this type vapour generator, guarantees that fluidic prime mover is the density difference between cold water post and the hot water post by the operation of natural circulation principle, and the steam of generation is saturation steam.Each saturation type vapour generator is made up of vertical cylindrical shell that has built-in carbonated drink separating device and the tube bank of inversion type U-shaped according to the vapour generator of transporting PWR nuclear power plant at full capacity.Each loop in one loop has a vapour generator, and it is a tubular type vapourizing unit vertically arranged, natural circulation.Whole device can be divided into: the bottom of feedwater evaporator section vapour generator evaporator section is to be made up of inverted 4640 inverted U-shaped tube banks.One loop water flows in pipe, and secondary circuit water is vaporization outside pipe.These pipes are welded on the thick manganese-molybdenum of 585mm-nickel (Mn-Mo-Ni) tube sheet, and a circuit pressure is born in tube sheet and tube bank.One loop water side seal head is made up of the cast steel hemispherical head, within it surface coverage stainless steel layer, and be divided into two inlet hydroeciums, outlet hydroecium through being welded in Inco nickel dividing plate on the tube sheet.Each hydroecium all has an adapter and a manhole of linking a loop.The whole vapourizing unit of natural circulation principle is placed in the metal cylinder cylindraceous, and the cylindrical shell bottom is connected with tube sheet, and its top links to each other with a bigger metal cylinder that comprises drying installation through a middle transition cone.The inlet of feedwater is positioned at the top of this cylindrical shell.
Accomplish for water dispenser by a looping pit pipe.Feedwater mixes with the water that drying plant is discharged, and in the formed annular space of cylindrical tole involucrum of being restrained by bottom cylindrical shell and encirclement, flows downward then.A space is arranged between involucrum bottom and tube sheet upper surface, and here water is heated near temperature of saturation, enters into then in the middle of the tube bank, upwards flows.
Keep the spacing of restraining by means of the dividing plate of vapour generator U-shaped tube bank, and between dividing plate, fix through pull bar.Have on 8 antidetonation dividing plates that some Kong Yirang pipe and water--vapour mixture passes through.In addition, dividing plate prevents that through some the chock of restraining body vibration is fixed on the bundle wrapper.Equally, the segmental arc in tube bank also is provided with the vibrationproof backstay.
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; Supply with water and flow with vertical direction, be heated simultaneously, be vaporized then along pipe; Steam gets into the steam turbine generating; Can cause vibrations with these pipe fluid in contact, need separate with the antidetonation dividing plate and prevent that damaged tubular from breaking, directly cause vapour generator and damage.For effectively preventing to isolate the vibrations of tube sheet, the cylinder lever connecting rod material that is provided with between the tube sheet plays keying action to the nuclear plant safety reliability service.
The vapour generator union lever 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 cylinder lever connecting rod material proposed strict demand.China is used to make still dependence on import of vapour generator cylinder lever connecting rod material at present; Therefore research and develop and make cylinder lever connecting rod 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 present invention provides a kind of nuclear power station steam generator with cylinder lever connecting rod material and preparation method thereof; Overcome existing vapour generator with the deficiency in the cylinder lever connecting rod material technology; This material price is low, composition is reasonable in design, ME is simple, has superior corrosion resistance, anti-tired
Labor, creep resistance and processability.
A kind of nuclear power station steam generator of the present invention is used the cylinder lever connecting rod material, its tensile strength 760-960MPa, and ys is greater than 590 MPa, and elongation is greater than 15%, and relative reduction in area is greater than 50%, HB 228-285HB, 0 ℃ of KV impact value is greater than 40J.
To achieve these goals, the present invention realizes through following technical scheme: a kind of nuclear power station steam generator is used the cylinder lever connecting rod material, counts by weight percentage, and ingredient is following:
C:0.080-0.015%; Si:0.10-1.0%; Mn:0.4-1.0%; P :≤0.030%; S :≤0.030%; Cr:11.5-13.5%; Ni:0.01-0.50%; Re:0.02-0.80%; Surplus is Fe and unavoidable impurities;
The purity of wherein said Si, Mn, Cr, Ni, Fe is all greater than 99%, and granularity is 20-50um; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
A kind of nuclear power station steam generator is used the cylinder lever connecting rod preparation methods, comprises the steps:
A, calculate with the weight percent meter of cylinder lever connecting rod material ingredient by nuclear power station steam generator and to carry out preparation of raw material:
C:0.080-0.015%; Si:0.10-1.0%; Mn:0.4-1.0%; P :≤0.030%; S :≤0.030%; Cr:11.5-13.5%; Ni:0.01-0.50%; Re:0.02-0.80%; Surplus is Fe and unavoidable impurities;
B, will add in the induction furnace in proper order by smelting by the raw material of aforementioned preparation and smelt, 1500 ℃~1580 ℃ of molten clear back temperature; The refining temperature during the deoxidation slag making wherein: 1550 ℃~1600 ℃, refining time was made white slag and was kept 15 minutes greater than 40 minutes; Wherein said norium Re adds tapping immediately in the molten steel in the induction furnace smelting was tapped preceding 2~3 minutes, adopt the argon shield method to cast during tapping;
C, esr, esr temperature: 1520 ℃~1580 ℃, melting voltage: 55/60V; Melting electric current: 5000/6000A;
D, forging, open the forging temperature: 1150 ℃, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=950 ℃;
F, quenching, 980 ℃~1050 ℃ of normalizing temperatures, hardening cooling;
G, tempering, 600 ℃~650 ℃ of tempering temperatures, water cooling or air cooling are but;
The surface frame divests the rod iron surface oxide layer and obtains vapour generator and use the cylinder lever connecting rod finished material.
Preparing method's of the present invention major technique characteristics are: adopt induction furnace to add the double melting method of electroslag remelting, make the degassing fully, again through the esr refining; Make molten steel clean, norium Re adds further quality and the mechanical property that improves vapour generator with cylinder lever connecting rod before tapping, through controlling forging ratio greater than 4; After hot rolling, quenching adds the control of operations such as tempering, finally obtains vapour generator and can reach 780-815MPa with the tensile strength of cylinder lever connecting rod material, and ys can reach 598 MPa; Elongation 18%; Shrinking percentage 52-75%, HB 228-285HB, 0 ℃ of impact value is greater than the vapour generator cylinder lever connecting rod material of 42-80J.
A kind of nuclear power station steam generator of the present invention is following with the principle of cylinder lever connecting rod material design mix:
C: very effective sclerosis and solution strengthening constituent element, stablize martensitic structure, proof strength, but usually occur as formation of crack, forming crisp sclerous tissues easily and cause delayed cracking like too high levels, its composition weight % is limited in 0.080-0.0150%;
Mn: deoxidation and desulfidation, guarantee the important element of oxidation-resistance, less than 0.01% can not obtain abundant deoxidation, surpasses 1 % intensity and reduces, and its composition weight % is limited in 0.4-1.0%;
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 0.1-1.0%;
Ni: improve toughness of material, the raising of intensity is also had contribution, its composition weight % is limited in 0.10-0.50%;
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 11.5-13.5%;
S, P: be inevitable detrimental impurity element in the material, its content is low more good more, its composition weight %, and P :≤0.030%, S :≤0.030%;
Re: add norium 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 0.02-0.80% among the present invention.
The employing nuclear power station steam generator that the present invention designed with the cylinder lever connecting rod material compared with prior art has following advantage:
1. composition is reasonable in design, cost is low, safe and reliable;
2. this vapour generator is with its tensile strength of cylinder lever connecting rod strip material 780-815MPa, and ys can reach 598 MPa, elongation 18%, and hardness 230-260, shrinking percentage 52-75%, HB 228-285HB, 0 ℃ of impact value is greater than 42-80J.Long term operation has higher-strength and corrosion resistance under 1000 ℃ of high temperature, its high temperature stress intensity stabilization;
3. because added micro-REE and the special preparation technology who has adopted double melting, guarantee that material has superior corrosion resistance, antifatigue, creep resistance and processability;
4. this nuclear power station steam generator is guaranteed the safe reliability of vapour generator with the cylinder lever connecting rod operation with the alternative import of cylinder lever connecting rod material, effectively prolongs the work-ing life of nuclear power station steam generator, reduces cost, and significantly improves economic benefit.For advancing the nuclear power domestic manufacture of key equipment that very significance is arranged.
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 nuclear power station steam generator is used the cylinder lever connecting rod material, counts by weight percentage, and ingredient is following:
C:0.080-0.015%; Si:0.10-1.0%; Mn:0.4-1.0%; P :≤0.030%; S :≤0.030%; Cr:11.5-13.5%; Ni:0.01-0.50%; Re:0.02-0.80%; Surplus is Fe and unavoidable impurities; The purity of wherein said Si, Mn, Cr, Ni, Ti, Fe is all greater than 99%, and granularity is 20-50um; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
A kind of nuclear power station steam generator is used the cylinder lever connecting rod preparation methods, comprises the steps: A, calculates with the weight percent meter of cylinder lever connecting rod material ingredient by nuclear power station steam generator and carry out preparation of raw material: C:0.080-0.015%; Si:0.10-1.0%; Mn:0.4-1.0%; P :≤0.030%; S :≤0.030%; Cr:11.5-13.5%; Ni:0.01-0.50%; Re:0.02-0.80%; Surplus is Fe and unavoidable impurities;
B, will add in the induction furnace in proper order by smelting by the raw material of aforementioned preparation and smelt, molten clear back temperature; The refining temperature during the deoxidation slag making wherein: 1550 ℃~1600 ℃, refining time was made white slag and was kept 15 minutes greater than 40 minutes; Wherein said norium Re adds tapping immediately in the molten steel in the induction furnace smelting was tapped preceding 2~3 minutes, adopt the argon shield method to cast during tapping;
C, esr, esr temperature: 1520 ℃~1580 ℃, melting voltage: 55/60V; Melting electric current: 5000/6000A;
D, forging, open the forging temperature: 1150 ℃, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=950 ℃;
F, quenching, 980 ℃~1050 ℃ of normalizing temperatures, hardening cooling;
G, tempering, 600 ℃~650 ℃ of tempering temperatures, water cooling or air cooling are but;
The surface frame divests the rod iron surface oxide layer and obtains vapour generator cylinder lever connecting rod finished material.
Nuclear power station steam generator of the present invention with the cylinder lever connecting rod material prepn 8 stove embodiment, wherein said embodiment 1-8 stove rod material ingredient and content % by weight calculate, as follows:
First stove: C:0.10%, Si:0.50%, Mn:0.85%, P:0.018%, S:0.004%, Cr:12.15%, Ni:0.11%, Re:0.03%;
Second stove: C:0.11%, Si:0.40%, Mn:0.80%, P:0.012%, S:0.005%, Cr:12.35%, Ni:0.13%, Re:0.04%;
The 3rd stove: C:0.12%, Si:0.60%, Mn:0.82%, P:0.014%, S:0.005%, Cr:12.45%, Ni:0.15%, Re:0.03%;
The 4th stove: C:0.13%, Si:0.55%, Mn:0.83%, P:0.010%, S:0.005%, Cr:12.50%, Ni:0.18%, Re:0.04%;
The 5th stove: C:0.125%, Si:0.65%, Mn:0.81%, P:0.013%, S:0.006%, Cr:12.42%, Ni:0.19%, Re:0.035%;
The 6th stove C:0.12%, Si:0.70%, Mn:0.82%, P:0.014%, S:0.008%, Cr:12.44%, Ni:0.18%, Re:0.04%;
The 7th stove C:0.12%, Si:0.350%, Mn:0.75%, P:0.013%, S:0.006%, Cr:12.56%, Ni:0.17%, Re:0.04%;
The 8th stove: C:0.12%, Si:0.40%, Mn:0.76%, P:0.012%, S:0.005%, Cr:12.51%, Ni:0.175%, Re:0.05%;
Above-mentioned eight stove embodiment its preparation methods are: select the ultralow-carbon pure iron for use; Prepare burden according to the present invention's eight stove embodiment design mix; Adopt duplex smelting process technology, the refining temperature when wherein induction furnace is smelted the deoxidation slag making: 1575 ℃, refining time is 60 minutes; White slag keeps 15 minutes → esr, refining temperature: 1575 ℃, melting voltage: 55/60V; The melting electric current: 5000/6000A → forging, open the forging temperature: 1150 ℃, final forging temperature: 1000 ℃ → hot rolling; Hot-rolled temperature: 1150 ℃, finishing temperature: 1000 ℃ → quench normalizing temperature: 1025 ℃, hardening cooling → tempering; 625 ℃ of tempering temperatures, water cooling or air cooling.
The nuclear power station steam generator that the embodiment of above 1-8 stove designs preparation has been supplied with in batches use with the pull bar strip material and has been got the nod, and through relevant department its composition, comprehensive mechanical property has been carried out detection, test, and examining report is following:
One. quality physical and chemical measuring room of east electric (Guangzhou) heavy-duty machine ltd
The material classification: vapour generator is used rod material.
Sample title: the present invention
Embodiment 1-8 stove, 1 in every stove, annealing, specification: ф 10mm,
Test basis: NPC-44300-JT116 Rev:C;
Technical qualification: NPC-44300-JT116 Rev:C;
Test temperature: room temperature,
1. mechanical property test
2. metallographic examination
Embodiment and mechanical property through above 1-8 stove detect; The nuclear power station steam generator that the present invention designed has with rod material that composition is reasonable in design, cost is low, stable manufacturing process; Have superior corrosion resistance, antifatigue, creep resistance and processability, guarantee safe and reliable.To enhancing productivity, effectively prolong the work-ing life of nuclear power station steam generator, reducing production costs has crucial economic implications.
Claims (2)
1. a nuclear power station steam generator is used the cylinder lever connecting rod material, it is characterized in that: count by weight percentage, ingredient is following:
C:0.080-0.015%;?Si:0.10-1.0%?;?Mn:?0.4-1.0%;?P:≤0.030%;?S:≤0.030%;?Cr:?11.5-13.5%;Ni:0.01-0.50%;?Re:0.02-0.80%;
Surplus is Fe and unavoidable impurities.
2. a kind of nuclear power station steam generator according to claim 1 is used the cylinder lever connecting rod material, it is characterized in that: the purity of wherein said Si, Mn, Cr, Ni, Fe is all greater than 99%, and granularity is 20-50um; Said rare earth Re is a norium, and its purity is greater than 99%, block 60*100mm.
A kind of nuclear power station steam generator is used the cylinder lever connecting rod preparation methods, it is characterized in that: comprise the steps:
A, calculate with the weight percent meter of cylinder lever connecting rod material ingredient by nuclear power station steam generator and to carry out preparation of raw material:
C:0.080-0.015%; Si:0.10-1.0%; Mn:0.4-1.0%; P :≤0.030%; S :≤0.030%; Cr:11.5-13.5%; Ni:0.01-0.50%; Re:0.02-0.80%; Surplus is Fe and unavoidable impurities;
B, will be suitable by smelting by the raw material of aforementioned preparation, order of addition(of ingredients) is that C-Fe-Ni-Cr-Si-Mn-Re adds in the induction furnace and smelts, molten clear back temperature is controlled at 1520 ℃~1580 ℃; Refining temperature: 1550 ℃~1600 ℃, refining time was made white slag and was kept 15 minutes greater than 40 minutes; Wherein said norium Re taps after in the induction furnace smelting was tapped preceding 2~3 minutes, melting clearly in the adding molten steel, and employing argon shield method is cast during tapping;
C, esr, esr temperature: 1520 ℃~1580 ℃, melting voltage: 55/60V; Melting electric current: 5000/6000A;
D, forging, open the forging temperature: 1150 ℃, final forging temperature >=950 ℃;
E, hot rolling, 1150 ℃ of hot-rolled temperatures, finishing temperature >=950 ℃;
F, quenching, 980 ℃~1050 ℃ of normalizing temperatures, hardening cooling;
G, tempering, 600 ℃~650 ℃ of tempering temperatures, water cooling or air cooling are but;
The rod iron surface oxide layer that surperficial frame divests final formation obtains vapour generator and uses the cylinder lever connecting rod finished material.
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Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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
- 2012-06-18 CN CN201210199380.7A patent/CN102732801B/en not_active Expired - Fee Related
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
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