CN109967674A - The manufacturing method of nuclear steam generator high temperature alloy forging - Google Patents
The manufacturing method of nuclear steam generator high temperature alloy forging Download PDFInfo
- Publication number
- CN109967674A CN109967674A CN201910222032.9A CN201910222032A CN109967674A CN 109967674 A CN109967674 A CN 109967674A CN 201910222032 A CN201910222032 A CN 201910222032A CN 109967674 A CN109967674 A CN 109967674A
- Authority
- CN
- China
- Prior art keywords
- forging
- steam generator
- high temperature
- manufacturing
- alloy
- 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.)
- Granted
Links
Classifications
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B21—MECHANICAL METAL-WORKING WITHOUT ESSENTIALLY REMOVING MATERIAL; PUNCHING METAL
- B21J—FORGING; HAMMERING; PRESSING METAL; RIVETING; FORGE FURNACES
- B21J5/00—Methods for forging, hammering, or pressing; Special equipment or accessories therefor
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C30/00—Alloys containing less than 50% by weight of each constituent
- C22C30/02—Alloys containing less than 50% by weight of each constituent containing copper
Abstract
The invention discloses a kind of nuclear steam generator manufacturing methods of high temperature alloy forging, comprising the following steps: step 1 provides a kind of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece;Step 2, the content for controlling O, N, Nb are as follows: O≤35ppm, N≤130ppm, Nb≤0.01%, wt;Step 3, the content for controlling Al and Ti element are as follows: Al is 0.37~0.45%, Ti is 0.37~0.45%, wt.Final forging of the invention meets the grain size and field trash testing requirements of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece, and mechanical behavior under high temperature meets standard detection requirement.
Description
Technical field
The present invention relates to a kind of manufacturing method of forging, especially a kind of nuclear steam generator high temperature alloy forging
Manufacturing method.
Background technique
A kind of Ni-Cr-Fe series austenite that 800H alloy system 19th century mid-term specialty metal company, the U.S. (SMS) develops is resistance to
Thermalloy has more excellent high temperature resistant, creep resistant and enduring quality since its carbon content increases compared with 800 alloys.It cuts
In the only end of the year in 2018, global first temperature gas cooled reactor steam generator manufactures in China to be completed, and Chinese Nuclear Power equipment manufactures and designs
It has marched toward again a new height.Steam generator is one of the equipment of most critical in high temperature gas cooled reactor nuclear power system, effect
It is that the heat of nuclear reactor is converted into the water vapour close to 600 DEG C, Turbo-generator Set is pushed to produce electricl energy.
Nuclear power temperature gas cooled reactor steam generator forging is ASME SB564 with the standard that 800H alloy manufactures main foundation,
Its respective material trade mark is Alloy UNS N08810.Nuclear power temperature gas cooled reactor steam generator in China's is forged with 800H alloy at present
Part is completely dependent on import, not yet progress localization, and is closed both at home and abroad to nuclear power temperature gas cooled reactor steam generator with 800H
The research of bodkin part is less, and controlling the two aspects to related field trash and grain size is even more to rarely have to be related to.
For the grain size of 800H alloy, the requirement in ASME SB564 to Alloy UNS N08810 alloy forged piece is 5
Grade is thicker, and the grain size of nuclear power temperature gas cooled reactor steam generator 800H alloy requires to be 2~5 grades.For 800H alloy
Forging, M23C6The beginning Precipitation Temperature of type carbide is higher, and about 1100 DEG C or so, due to M23C6The presence of type carbide is to forging
The forming core and crystal grain of part recrystallization grow up and all have larger impact, therefore the controlling difficulties of its grain size are how to control M23C6Type
The form and distribution of carbide make forging even tissue to control the grain size of 800H alloy forged piece, to improve the high temperature of forging
Mechanical property simultaneously makes its stabilisation, this one of maximum difficult point manufactured for the type forging.
Summary of the invention
The technical problem to be solved by the present invention is to be ground for nuclear power temperature gas cooled reactor steam generator with high temperature alloy forging
Study carefully a set of stabilization, reliable manufacturing process out.
In order to solve the above-mentioned technical problem, the invention discloses a kind of nuclear steam generator systems of high temperature alloy forging
Make method, comprising the following steps:
Step 1 provides a kind of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece;
Step 2, the content for controlling O, N, Nb are as follows: O≤35ppm, N≤130ppm, Nb≤0.01%, wt;Step 3,
The content for controlling Al and Ti element is as follows: Al is 0.37~0.45%, Ti is 0.37~0.45%, wt.
Preferably, further includes: step 4, the content for controlling Cu element are as follows: Cu≤0.10%, wt.
Preferably, further includes: step 5, by the 800H alloy smelting after step 4 at electrode bar, and refusion and smelting is at electricity
Slag ingot, the ingredient and its percentage of alloying element included by the ESR ingot are as follows: C is 0.075~0.095%, Cr 21.5
~22.5%, Ni be 33.0~34.0%, Fe >=39.5%, Al be 0.37~0.45%, Ti be 0.37~0.45%, Cu≤
0.10%, Si are that 0.40~0.60%, Mn is 0.90~1.10%, Nb≤0.01%, O≤35ppm, N≤130ppm, wt.
Preferably, further include following steps: before steel ingot forging, by Heating Steel Ingots to 1180~1210 DEG C, heat preservation 20 is small
When, it is forged after heat preservation with 10 tons of Single arms, it is 1180 ± 10 DEG C that forging, which melts down heat preservation degree, and soaking time is no more than 2
Hour.
Preferably, further include following steps: final forging temperature is controlled at 1100 DEG C or more, and forging is stood after forging
Carry out water cooling.
It preferably, further include the workflow that solution heat treatment is carried out after forging process for fuel, the workflow packet
It includes:
Workflow one, furnace temperature≤600 DEG C sample enters furnace, and is warming up to 870 DEG C with~200 DEG C/h of heating rate
It is kept the temperature.
Preferably, further includes: workflow two is warming up to as quickly as possible after sample keeps the temperature 2 hours in 870 DEG C of simulation furnaces
1125±10℃。
Preferably, further includes: workflow three, sample keep the temperature 3~5 hours in 1125 ± 10 DEG C of simulation furnaces.
Preferably, further includes: workflow four, water cooling of coming out of the stove immediately after sample heat preservation.
Detailed description of the invention
Fig. 1 is the manufacturing method schematic diagram of nuclear steam generator high temperature alloy forging of the invention.
Fig. 2 is 800H alloy steel ingot Forge Heating schematic diagram.
Fig. 3 is 800H alloy forged piece solid solution in the manufacturing method of nuclear steam generator high temperature alloy forging of the invention
Heat treatment process schematic diagram.
Specific embodiment
Specific embodiments of the present invention are described in detail with reference to the accompanying drawing.It is to be appreciated that the present invention is not
It is confined to above-mentioned particular implementation, devices and structures not described in detail herein should be understood as with common in this field
Mode is practiced;Anyone skilled in the art without departing from the scope of the technical proposal of the invention all can benefit
Many possible changes and modifications are made to technical solution of the present invention with the methods and technical content of the disclosure above, or are revised as
With the equivalent embodiment of variation, this is not affected the essence of the present invention.
In the prior art, nuclear power temperature gas cooled reactor steam generator forging requires such as the following table 1 with 800H alloy composition
It is shown.
1 800H of table (Alloy UNS N08810) alloy composition requires (wt, %)
Element | C | Mn | S | Si | Ni |
Chemical composition analysis % | 0.05~0.10 | ≤1.50 | ≤0.015 | ≤1.00 | 30.0~35.0 |
Element | Cr | Fe | Al | Ti | Cu |
Chemical composition analysis % | 19.0~23.0 | ≥39.5 | 0.15~0.60 | 0.15~0.60 | ≤0.75 |
For the Control and Inclusion Removal of 800H alloy forged piece, in ASME SB564 simultaneously to Alloy UNS N08810 alloy forged piece
It is not required, and the field trash testing requirements of nuclear power temperature gas cooled reactor steam generator 800H alloy are as shown in table 2.
2 nuclear steam generator of table 800H microstructure of the alloy testing requirements
Due to the complexity that the field trash in high temperature alloy is formed and grown up, forging alloying component and its manufacturing process can
To in forging field trash pattern, size, affect greatly at being grouped as and be distributed.As shown in table 1, it is closed in nuclear power with 800H
The alloying component of bodkin part does not make related request to residual elements niobium (Nb) in requiring, but in the actual production process of forging
In, due to not being added on control to niobium element in the raw material selection and the setting of smelting process of electrode bar smelting, content is usual
Fall between 0.01~0.10% (wt), this by forging field trash pattern, size, at be grouped as and be distributed cause it is larger
It influences, keeps forging B class and D class Ti (C, N) field trash exceeded, and finally influence forging comprehensive performance.
In addition, for Alloy UNS N08810 alloy, not to its height suitable for the standard ASME SB564 of forging
Warm mechanical property claims, and nuclear power temperature gas cooled reactor steam generator is come from the requirement of the mechanical behavior under high temperature of 800H alloy
In ASME SB163 (being suitable for tubing), specific requirement is as shown in table 3.
The 800H alloy mechanical performance requirement of 3 nuclear steam generator of table
Since forging's block dimension is significantly greater than tubing, this proposes higher want to the design of the manufacturing process of forging
It asks.Forging crystal grain, field trash and M23C6The form of type carbide and distribution also to the high-temperature behavior of 800H alloy forged piece exist compared with
It is big to influence.
Grain size, field trash for nuclear power temperature gas cooled reactor steam generator listed by table 2 and table 3 with 800H alloy forged piece
And mechanical behavior under high temperature testing requirements, the invention discloses a kind of nuclear steam generator high temperature alloy forging as shown in Figure 1
Manufacturing method is controlled by quantity, pattern and the size of field trash in 800H alloy forged piece, is specifically included for optimization of Chemical Composition
Following steps:
Step 1 provides a kind of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece.
Step 2, the content for controlling O, N, Nb are as follows: O≤35ppm, N≤130ppm, Nb≤0.01%, wt.
Step 3, the content for controlling Al and Ti element are as follows: Al is 0.37~0.45%, Ti is 0.37~0.45%, wt.
Step 4, the content for controlling Cu element are as follows: Cu≤0.10%, wt.
Step 5 by the 800H alloy smelting after step 4 at electrode bar, and carries out electroslag remelting, and the electrode bar is wrapped
The ingredient and percentage included are as follows: C be 0.075~0.095%, Cr be 21.5~22.5%, Ni be 33.0~34.0%, Fe >=
39.5%, Al are that 0.37~0.45%, Ti is 0.37~0.45%, Cu≤0.10%, and Si is 0.40~0.60%, Mn 0.90
~1.10%, Nb≤0.01%, O≤35ppm, N≤130ppm, wt.
In above step, since Al and Ti element is two kinds of alloy strengthening elements in 800H alloy, one side and Ni
Element combines and forms γ ' phase (Ni3Al and Ni3Ti phase), invigoration effect is played to 800H alloy forged piece;On the other hand, Al and Ti member
Element has the function of certain solution strengthening in the alloy.And two elemental gas of O and N will form Al with Al and Ti respectively2O3And
Three type impurity of TiN, Ti (C, N), if also containing other impurity elements easily in conjunction with C and N element, Ti (C, N) in forging matrix
Complex inclusion will be formed with other alloying elements.Through studying, in the case that Nb content is 0.05%, wt in the sample, just shape
At a large amount of (Ti, Nb) (C, N) complex inclusion, (Ti, Nb) (C, N) complex inclusion is relatively large sized, and is gathered into
Chainlike distribution.Through studying, Al2O3, TiN, (Ti, Nb) (C, N) three classes main inclusions can individually forming core grow up, also can be with it
Its field trash forms complex inclusion, and is gathered into chain or bulk distribution.
Due to the Al2O3, TiN, (Ti, Nb) (C, N) three type impurity presence, will reduce alloy in γ ' mutually and solid solution state
The content of Al and Ti element, to influence the comprehensive mechanical property of 800H alloy forged piece.According in the above reason, O and N two are controlled
The content of gaseous impurity element is as follows: O≤35ppm, N≤130ppm, wt.
In addition, it is observed that single inclusion size is maximum in the 800H alloy of amount containing Nb higher (0.05%, wt), chain
The field trash that shape is longest, quantity is most is (Ti, Nb) (C, N), therefore controls the main of field trash in 800H alloy and arrange
It applies to control the Nb element in alloy, reduces the formation of (Ti, Nb) (C, N) complex inclusion to the greatest extent.In view of electrode bar produces
Cost and (Ti, Nb) (C, N) complex inclusion two factors of influence scale, require the content control of Nb element in the present invention
System is within the scope of≤0.01%, wt.It is observed that control Nb constituent content 800H alloy field trash sample (Nb content are as follows:≤
0.01%, wt) in main field trash be mingled with for TiN, and containing a small amount of and lesser (Ti, Nb) (C, the N) duplex impurity of size and
Al2O3It is mingled with, pattern, size, quantity and the distribution of the field trash in sample have obtained preferable control.
Meanwhile in order to improve the intensity and other comprehensive performances of nuclear power high temperature gas cooled reactor 800H alloy, by tri- kinds of C, Cr, Ni
Alloying element controls the upper limit in standard requirements range;Al, the Ti two for easily forming field trash with foreign gas element is closed simultaneously
Gold element controls the middle limit in standard requirements range;To reduce Cu element shape during ingot solidification or forging cool down at a slow speed
At phase containing Cu, the lower limit in standard requirements range is controlled;Finally by two kinds of elements of Si and Mn by standard requirements range
Limit control, the residual elements such as P, S, As, Sn, Sb, Bi, Pb, Co are pressed related nuclear power standard requirements and are executed.
Specific control requires are as follows: it be 21.5~22.5%, Ni is 33.0~34.0%, Al that C, which is 0.075~0.095%, Cr,
It is 0.37~0.45%, Cu≤0.10% for 0.37~0.45%, Ti, Si is that 0.40~0.60%, Mn is 0.90~1.10%,
wt。
Embodiment two
As shown in Figure 1, on the basis of example 1, controlling the Forge Heating temperature and heating and thermal insulation of 800H alloy forged piece
Time.
It is observed that harmful field trash in 800H alloy starts forming core and is grown up during solidification of molten steel, and in molten steel
Field trash will further grow up after solidification, in addition, just having M at about 1100 DEG C or so23C6Type carbide starts to be precipitated.For in electricity
Nuclear power temperature gas cooled reactor steam generator forging is closed with 800H in such a way that ingot mould leads to cooling water in slag reflow process
In the case that golden steel ingot carries out cooling, since steel ingot size is larger, the cooling velocity of steel ingot is still limited, solidification of molten steel cooling procedure
In still will form a degree of dendritic segregation, alloying elements distribution is uneven, and (Ti, Nb) (C, N) complex inclusion is in molten steel
The forward position of solidification is formed;M in steel ingot cooling procedure23C6Type carbide is formed in normal segregation area;The forming position that TiN is mingled with is unlimited
In normal segregation area.
For the crystal grain of 800H alloy forged piece after forging and solution heat treatment, a factor the most significant is influenced
As M23C6The precipitation and distribution situation of type carbide, through studying, in a poor embodiment, steel ingot is not carried out uniformly before forging
Change processing, M is largely precipitated in normal segregation area after forging solution heat treatment23C6Type carbide, forging crystal grain are 4 grades;And negative segregation area
Without M23C6Type carbide, which grows up to crystal grain, generates drag interaction, and crystal grain is grown up obviously, is 2 grades.Therefore to make forging after forging can
Form uniform crystal grain, and carry out forging crystal grain during solution heat treatment reheats in forging can uniformly grow up, it need to be
Homogenization Treatments, as far as possible the dendritic segregation degree in reduction steel ingot are carried out before steel ingot forging, are uniformly distributed alloying element.
Therefore, the present invention claims before forging to nuclear power temperature gas cooled reactor steam generator forging with 800H alloy steel ingot into
Row Homogenization Treatments, homogenization holding temperature is 1180~1210 DEG C, for steel ingot of the present invention (steel ingot representative section ruler
Very little~550mm) for, homogenization soaking time is 20 hours.
Embodiment three
As shown in Figure 1, on the basis of example 2, being forged after the final forging temperature and forging that control 800H alloy forged piece
The type of cooling of part.
As previously mentioned, 800H alloy forged piece just has M at 1100 DEG C or so23C6Type Carbide Precipitation, in order to reduce to the greatest extent
M23C6The precipitation of type carbide should as far as possible control the final forging temperature of forging at 1100 DEG C or more, and forging terminates in forging
Carry out water cooling immediately afterwards.
Example IV
In the technology of embodiment three, for the M of 800H alloy forged piece23C6The precipitation feature of type carbide, design are reasonable
Solution heat treatment.
For nuclear power temperature gas cooled reactor steam generator forging 800H alloy, the control of mechanical behavior under high temperature exists
It is largely dependent upon in the selection of forging heating speed and the determination of forging solid solution holding temperature and soaking time.800H is closed
Though having carried out water cooling after golden forging process for fuel knot speed, it inevitably has part M23C6Type carbide is precipitated in the alloy,
For forging the main apparent forging of machine direction, according to its deformation characteristics, M23C6Type carbide is easily along forging master
Machine direction is in band-like precipitation;In addition, if being carried out by the way of slow heat during the solution heat treatment of 800H alloy forged piece
Heating, it will have a large amount of M23C6Type carbide is in band-like precipitation during heating, due to this in forging solid solution insulating process
The M of the band-like precipitation of kind23C6Type carbide has certain pinning drag interaction, M to crystal boundary23C6The more area of type Carbide Precipitation
Domain crystal grain is more difficult to grow up, and M23C6The less region of type Carbide Precipitation, after certain soaking time, crystal grain is grown up rapidly,
Cause forging mixed crystal.
Based on the above analysis, during the solution heat treatment of 800H alloy forged piece, emphasis need to forging heating speed into
Row control, to reduce M23C6Type carbide is precipitated during heating;It on the other hand is control forging soaking time, to prevent forging
Crystal grain is locally grown up, and forging mixed crystal is caused.As shown in Figure 3.
The present invention develops a set of stabilization, reliable with 800H alloy forged piece for nuclear power temperature gas cooled reactor steam generator
Manufacturing process, to reach its requirement, including Design of Chemical Composition, grain size and Control and Inclusion Removal etc..Of the invention
Final forging meets the grain size and field trash testing requirements of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece, high
Warm mechanical property meets standard detection requirement.
The sampled completion solution heat treatment test of the present invention, field trash, grain size and the mechanical performance detection of final forging
As a result meet high temperature gas cooled reactor nuclear power evaporator forging technical requirements, forging comprehensive mechanical property is good.Using skill of the invention
The specific Physico-chemical tests result of forging of art scheme manufacture is as shown in table 4~5:
The forging metallographic testing result of the present invention of table 4
The forging mechanical performance testing result of the present invention of table 5
Presently preferred embodiments of the present invention is described above, anything that does not depart from the technical scheme of the invention, according to
According to technical spirit any simple modifications, equivalents, and modifications made to the above embodiment of the invention, this hair is still fallen within
In the range of bright technical solution protection.
Claims (9)
1. a kind of nuclear steam generator manufacturing method of high temperature alloy forging, which comprises the following steps:
Step 1 provides a kind of nuclear power temperature gas cooled reactor steam generator 800H alloy forged piece;
Step 2, the content for controlling O, N, Nb are as follows: O≤35ppm, N≤130ppm, Nb≤0.01%, wt;
Step 3, the content for controlling Al and Ti element are as follows: Al is 0.37~0.45%, Ti is 0.37~0.45%, wt.
2. the nuclear steam generator as described in claim 1 manufacturing method of high temperature alloy forging, which is characterized in that also wrap
It includes:
Step 4, the content for controlling Cu element are as follows: Cu≤0.10%, wt.
3. the nuclear steam generator as described in claim 1 manufacturing method of high temperature alloy forging, which is characterized in that also wrap
It includes:
Step 5, by the 800H alloy smelting after step 4 at electrode bar, and refusion and smelting, at ESR ingot, the ESR ingot is wrapped
The ingredient and its percentage of the alloying element included are as follows: C be 0.075~0.095%, Cr be 21.5~22.5%, Ni be 33.0~
It is 0.37~0.45%, Cu≤0.10% that 34.0%, Fe >=39.5%, Al, which are 0.37~0.45%, Ti, Si is 0.40~
0.60%, Mn are 0.90~1.10%, Nb≤0.01%, O≤35ppm, N≤130ppm, wt.
4. manufacturing method of the nuclear steam generator with high temperature alloy forging as described in one of claims 1 to 3, feature
It is, further includes following steps:
Steel ingot forging before, by Heating Steel Ingots to 1180~1210 DEG C, keep the temperature 20 hours, after heat preservation with 10 tons of Single arms into
Row forging, it is 1180 ± 10 DEG C that forging, which melts down holding temperature, and soaking time is no more than 2 hours.
5. manufacturing method of the nuclear steam generator with high temperature alloy forging as described in one of claims 1 to 3, feature
It is, further includes following steps: final forging temperature is controlled at 1100 DEG C or more, and forging carries out water immediately after forging
It is cold.
6. manufacturing method of the nuclear steam generator with high temperature alloy forging as described in one of claims 1 to 3, feature
It is, further includes the workflow for carrying out solution heat treatment after forging process for fuel, the workflow includes:
Workflow one, furnace temperature≤600 DEG C sample enters furnace, and is warming up to 870 DEG C of progress with~200 DEG C/h of heating rate
Heat preservation.
7. the nuclear steam generator as claimed in claim 6 manufacturing method of high temperature alloy forging, which is characterized in that also wrap
It includes:
Workflow two is warming up to 1125 ± 10 DEG C after sample keeps the temperature 2 hours in 870 DEG C of simulation furnaces as quickly as possible.
8. the nuclear steam generator as claimed in claim 7 manufacturing method of high temperature alloy forging, which is characterized in that also wrap
It includes:
Workflow three, sample keep the temperature 3~5 hours in 1125 ± 10 DEG C of simulation furnaces.
9. the nuclear steam generator as claimed in claim 8 manufacturing method of high temperature alloy forging, which is characterized in that also wrap
It includes:
Workflow four, water cooling of coming out of the stove immediately after sample heat preservation.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201910222032.9A CN109967674B (en) | 2019-03-22 | 2019-03-22 | Manufacturing method of high-temperature alloy forging for nuclear power steam generator |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201910222032.9A CN109967674B (en) | 2019-03-22 | 2019-03-22 | Manufacturing method of high-temperature alloy forging for nuclear power steam generator |
Publications (2)
Publication Number | Publication Date |
---|---|
CN109967674A true CN109967674A (en) | 2019-07-05 |
CN109967674B CN109967674B (en) | 2020-12-08 |
Family
ID=67080110
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201910222032.9A Active CN109967674B (en) | 2019-03-22 | 2019-03-22 | Manufacturing method of high-temperature alloy forging for nuclear power steam generator |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN109967674B (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN114107826A (en) * | 2021-12-06 | 2022-03-01 | 浙江大隆合金钢有限公司 | Nickel-based high-temperature alloy and preparation method thereof |
CN115287523A (en) * | 2022-07-19 | 2022-11-04 | 山西太钢不锈钢股份有限公司 | Process method for reducing nitrogen content of iron-based heat-resistant alloy |
CN117265440A (en) * | 2023-09-25 | 2023-12-22 | 浙江大隆特材有限公司 | Preparation method of nickel-based superalloy forging |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106133161A (en) * | 2014-03-14 | 2016-11-16 | 奥贝特迪瓦尔公司 | Parts that the nickel alloy of precipitation-hardening, described alloy are made and manufacture method thereof |
CN107760990A (en) * | 2017-10-24 | 2018-03-06 | 上海申江锻造有限公司 | The forging method of nuclear steam generator flange forge piece |
CN109136652A (en) * | 2017-06-15 | 2019-01-04 | 宝钢特钢有限公司 | Nuclear power key equipment nickel-base alloy extrusion bar of large cross section and its manufacturing method |
CN109136653A (en) * | 2017-06-15 | 2019-01-04 | 宝钢特钢有限公司 | For the nickel-base alloy of nuclear power generating equipment and its manufacturing method of hot rolled plate |
-
2019
- 2019-03-22 CN CN201910222032.9A patent/CN109967674B/en active Active
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN106133161A (en) * | 2014-03-14 | 2016-11-16 | 奥贝特迪瓦尔公司 | Parts that the nickel alloy of precipitation-hardening, described alloy are made and manufacture method thereof |
CN109136652A (en) * | 2017-06-15 | 2019-01-04 | 宝钢特钢有限公司 | Nuclear power key equipment nickel-base alloy extrusion bar of large cross section and its manufacturing method |
CN109136653A (en) * | 2017-06-15 | 2019-01-04 | 宝钢特钢有限公司 | For the nickel-base alloy of nuclear power generating equipment and its manufacturing method of hot rolled plate |
CN107760990A (en) * | 2017-10-24 | 2018-03-06 | 上海申江锻造有限公司 | The forging method of nuclear steam generator flange forge piece |
Non-Patent Citations (3)
Title |
---|
李冬升: "奥氏体不锈钢的计算设计和核电蒸发器传热管材料的研究开发", 《中国博士学位论文全文数据库 工程科技Ⅱ辑(月刊)》 * |
王黎云: "Incoloy-800H合金的成分与结构特征", 《特殊钢》 * |
龚豹,张国花: "固溶处理对800H高温合金力学性能的影响", 《大型铸锻件》 * |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN114107826A (en) * | 2021-12-06 | 2022-03-01 | 浙江大隆合金钢有限公司 | Nickel-based high-temperature alloy and preparation method thereof |
CN115287523A (en) * | 2022-07-19 | 2022-11-04 | 山西太钢不锈钢股份有限公司 | Process method for reducing nitrogen content of iron-based heat-resistant alloy |
CN115287523B (en) * | 2022-07-19 | 2023-12-29 | 山西太钢不锈钢股份有限公司 | Technological method for reducing nitrogen content of iron-based heat-resistant alloy |
CN117265440A (en) * | 2023-09-25 | 2023-12-22 | 浙江大隆特材有限公司 | Preparation method of nickel-based superalloy forging |
Also Published As
Publication number | Publication date |
---|---|
CN109967674B (en) | 2020-12-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN107937831B (en) | Pressure vessel 12Cr2Mo1V steel alloy and its forging heat treatment process | |
CN108441705A (en) | A kind of high intensity ni-base wrought superalloy and preparation method thereof | |
CN102477518B (en) | Steel used for steam turbine blades and manufacturing method thereof | |
CN104630597B (en) | A kind of iron nickel and chromium high temperature alloy and its manufacture method | |
CN113235030B (en) | Preparation method of large-size GH4169 high-temperature alloy bar | |
CN109967674A (en) | The manufacturing method of nuclear steam generator high temperature alloy forging | |
CN103614649A (en) | High-strength, high-toughness and high-plasticity martensitic stainless steel and preparation method thereof | |
CN109022925B (en) | Method for reducing Laves phase in nickel-based superalloy steel ingot | |
CN106435281B (en) | High-lasting strength nickel-base alloy and preparation method thereof | |
CN109112408A (en) | The manufacturing method of the heat-resisting steel forgings of big specification P92 | |
CN102650020A (en) | High-silicon high-manganese type high-thermal stability hot work die steel and thermal treatment process thereof | |
CN110106398A (en) | A kind of low chromium corrosion-proof and high-strength polycrystalline high temperature alloy and preparation method thereof | |
CN109136652A (en) | Nuclear power key equipment nickel-base alloy extrusion bar of large cross section and its manufacturing method | |
CN106756509B (en) | A kind of high-temperature alloy structural steel and its Technology for Heating Processing | |
CN110408850A (en) | The super-steel and preparation method thereof of nanocrystalline intermetallics precipitation strength | |
CN110484841A (en) | A kind of heat treatment method of GH4780 alloy forged piece | |
CN109136719A (en) | A kind of ageing strengthening type Ni-Cr base high-temperature corrosion-resistant alloy and heat treatment method | |
CN102321818A (en) | Method for smelting cast nickel base alloy K417G return | |
CN105331905A (en) | Novel non-magnetic stainless steel and preparation method thereof | |
CN109554609A (en) | Exempt from the austenitic heat-resistance steel and its manufacturing method of peeling in a kind of surface | |
CN110408835A (en) | Rare-earth type microalloying high carbon martensite stainless steel and preparation method thereof | |
CN107974632B (en) | Austenite hot-work die steel and preparation method thereof | |
CN110331352A (en) | A kind of diameter forging method controlling nickel-base alloy distribution of carbides | |
CN109898028A (en) | Austenite heat-resistance stainless steel of resistance to high temperature oxidation and preparation method thereof and purposes | |
CN106636850B (en) | High-temperature oxidation resistance high intensity mixes rare-earth alloy material and preparation method |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |