CN115852250A - F91 alloy steel forging for fast reactor nuclear power station and production process thereof - Google Patents
F91 alloy steel forging for fast reactor nuclear power station and production process thereof Download PDFInfo
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- 238000005242 forging Methods 0.000 title claims abstract description 81
- 229910000851 Alloy steel Inorganic materials 0.000 title claims abstract description 38
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 19
- 238000010438 heat treatment Methods 0.000 claims abstract description 31
- 239000002994 raw material Substances 0.000 claims abstract description 5
- 238000007670 refining Methods 0.000 claims abstract description 5
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical group [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims description 26
- 229910000831 Steel Inorganic materials 0.000 claims description 16
- 239000010959 steel Substances 0.000 claims description 16
- 238000005496 tempering Methods 0.000 claims description 16
- 229910052742 iron Inorganic materials 0.000 claims description 13
- 238000001514 detection method Methods 0.000 claims description 7
- 238000010791 quenching Methods 0.000 claims description 7
- 230000000171 quenching effect Effects 0.000 claims description 7
- 239000000126 substance Substances 0.000 claims description 5
- 238000000034 method Methods 0.000 abstract description 10
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 11
- 239000000463 material Substances 0.000 description 7
- 239000000203 mixture Substances 0.000 description 4
- 230000000052 comparative effect Effects 0.000 description 3
- 239000000956 alloy Substances 0.000 description 2
- 239000013078 crystal Substances 0.000 description 2
- 238000005520 cutting process Methods 0.000 description 2
- 238000009863 impact test Methods 0.000 description 2
- 238000009864 tensile test Methods 0.000 description 2
- 230000007704 transition Effects 0.000 description 2
- 238000007546 Brinell hardness test Methods 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 229910001566 austenite Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000002045 lasting effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000002085 persistent effect Effects 0.000 description 1
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Abstract
The invention provides an F91 alloy steel forging for a fast reactor nuclear power station, which comprises the following components in percentage by weight: c is between 0.08 and 0.12 percent; si is more than or equal to 0.20 percent and less than or equal to 0.50 percent; mn is more than or equal to 0.30 percent and less than or equal to 0.60 percent; p is less than or equal to 0.020%; s is less than or equal to 0.010 percent; cr is between 9.00 and 9.50 percent; mo is more than or equal to 0.90 percent and less than or equal to 1.05 percent; v is more than or equal to 0.20 percent and less than or equal to 0.25 percent; n is more than or equal to 0.030% and less than or equal to 0.070%; nb is more than or equal to 0.06 percent and less than or equal to 0.10 percent; ni is less than or equal to 0.40 percent; al is less than or equal to 0.02 percent; ti is less than or equal to 0.01 percent; zr is less than or equal to 0.01 percent; cu is less than or equal to 0.10 percent; sn is less than or equal to 0.005 percent; as is less than or equal to 0.010 percent; sb is less than or equal to 0.003 percent; pb is less than or equal to 0.008 percent; bi is less than or equal to 0.008 percent; the invention also discloses a production process of the F91 alloy steel forging for the fast reactor nuclear power station, which comprises the following steps: s1, refining raw materials; s2, forging; s3, heat treatment; and S4, detecting. By the method, the final alloy steel forging can meet the requirements of the fast reactor nuclear power station.
Description
Technical Field
The invention relates to the field of alloy material forging, in particular to an F91 alloy steel forging for a fast reactor nuclear power station and a production process thereof.
Background
The fast neutron reactor belongs to a fourth generation nuclear reactor type, F91 alloy steel forgings are used in a certain fast reactor in a large quantity, and the forgings are applied to important parts of a nuclear power station and have high requirements on the performance of the forgings, and detection results of a conventional F91 alloy steel such as endurance test, high-temperature stretching and 0-degree impact energy cannot meet the requirements.
Meanwhile, because the difference between the fast reactor and the pressurized water reactor is large, the performance requirements of the fast reactor on the forged piece are different from those of other pressurized water reactor nuclear power stations. In order to arrange in advance and increase market share of future fourth-generation nuclear reactor type forgings, the fast reactor F91 alloy steel forgings are researched and developed by our company.
Disclosure of Invention
In order to solve the problems, the invention provides an F91 alloy steel forging for a fast reactor nuclear power station and a production process thereof.
The main content of the invention comprises: an F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in parts by weight:
c is more than or equal to 0.08 percent and less than or equal to 0.12 percent; si is more than or equal to 0.20 percent and less than or equal to 0.50 percent; mn is more than or equal to 0.30 percent and less than or equal to 0.60 percent; p is less than or equal to 0.020%; s is less than or equal to 0.010 percent; cr is between 9.00 and 9.50 percent; mo is more than or equal to 0.90 percent and less than or equal to 1.05 percent; v is more than or equal to 0.20 percent and less than or equal to 0.25 percent; n is more than or equal to 0.030% and less than or equal to 0.070%; nb is more than or equal to 0.06 percent and less than or equal to 0.10 percent; ni is less than or equal to 0.40 percent; al is less than or equal to 0.02 percent; ti is less than or equal to 0.01 percent; zr is less than or equal to 0.01 percent; cu is less than or equal to 0.10 percent; sn is less than or equal to 0.005 percent; as is less than or equal to 0.010 percent; sb is less than or equal to 0.003 percent; pb is less than or equal to 0.008 percent; bi is less than or equal to 0.008 percent, and the balance is iron.
Preferably, wherein (C + N) is more than or equal to 0.12 percent, N can replace C, and the strength of the material is increased.
Preferably, the ratio of N/Al is greater than or equal to 4, the ratio of N/Al is increased, the plasticity of the steel is improved, and the ductile-brittle transition temperature and the non-plastic transition temperature are reduced.
Preferably, wherein (As + Sn + Sb + Pb) is ≦ 0.020%.
Preferably, wherein (As + Sn + Sb + Pb) ≦ 0.015%, harmful elements, the lower the better.
The invention also discloses a production process of the F91 alloy steel forging for the fast reactor nuclear power station, which comprises the following steps:
s1, raw material refining: refining the raw materials outside an electric furnace into an alloy steel ingot containing the chemical components;
s2, forging: and forging the obtained alloy steel ingot into an alloy steel forging by using a press, wherein the total forging ratio of the forging is more than 3, the initial forging temperature is 1220 ℃, the final forging temperature is more than or equal to 800 ℃, the riser part of the steel ingot is removed by 15 percent, and the nozzle part of the steel ingot is removed by 5 percent.
S3, heat treatment: the heating temperature during normalizing or quenching is 1040-1080 ℃, and the tempering temperature is 750-780 ℃;
s4, detection: and performing performance detection and nondestructive detection on the alloy steel forging subjected to heat treatment.
Preferably, the press in S2 is a 3600 ton press.
Preferably, in S3, when the cross-sectional thickness is more than 75mm during heat treatment, the heat treatment is quenching and tempering, the heating temperature during quenching is 1040-1080 ℃, and the tempering temperature is 750-780 ℃.
Preferably, the total forging ratio of the forging in S2 is greater than 4.5.
The invention has the beneficial effects that:
1. in the traditional F91 alloy steel forging, cr is more than or equal to 8.00 percent and less than or equal to 9.50 percent; mo is between 0.85 and 1.05 percent; v is between 0.18 and 0.25 percent, and in the alloy component of the invention, cr is between 9.00 and 9.50 percent; mo is more than or equal to 0.90 percent and less than or equal to 1.05 percent; v is more than or equal to 0.20% and less than or equal to 0.25%, the increase of Gr element can improve the strength, hardness and wear resistance of the material, and can also improve the hardenability during heat treatment, the increase of Mo element can refine crystal grains, improve the heat strength performance of the material, improve the high-temperature endurance strength and creep strength, and the increase of V element can prevent austenite crystal grains from coarsening, improve the strength of the material and the like;
2. the total forging ratio of the forge piece is more than 3, the initial forging temperature is 1220 ℃, the final forging temperature is more than or equal to 800 ℃, the as-cast structure can be effectively eliminated, the density of the material is increased, and the micro defects are forged, so that the lasting strength and the fatigue strength of the material are effectively improved;
3. the heating temperature during normalizing or quenching is 1040-1080 ℃, the tempering temperature is 750-780 ℃, an expected heat treatment structure is obtained, the performance of the forging piece is excellent, and the final alloy steel forging piece can meet the requirements of a fast reactor nuclear power station.
Detailed Description
The technical solution protected by the present invention is specifically explained below.
Selecting a blank steel ingot made of SA182 MF 91, adopting a 3600-ton press as forging equipment, cutting off more than or equal to 10% of an ingot head, cutting off more than or equal to 5% of an ingot tail, using an industrial resistance furnace as heat treatment equipment, monitoring by using an automatic disc paper instrument, and adopting an XLS-144M3 water circulation cooling pool.
Example 1
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.092%; si:0.36 percent; mn:0.39 percent; p:0.012%; s:0.006%; : cr:9.32 percent; : mo:0.92 percent; v:0.22 percent; n:0.061%; nb:0.075%; ni:0.36 percent; al:0.012%; ti:0.006%; zr:0.005 percent; cu:0.03 percent; sn:0.003%; as:0.007%; sb:0.002%; pb:0.006%; bi:0.003% of iron and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 820 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1050 ℃, and the tempering temperature is 750 ℃.
Example 2
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.096%; si:0.39 percent; mn:0.51 percent; p:0.011 percent; s:0.005 percent; : cr:9.26 percent; : mo:0.92 percent; v:0.21 percent; n:0.066%; nb:0.082%; ni:0.32 percent; al:0.011 percent; ti:0.005 percent; zr:0.006%; cu:0.05 percent; sn:0.003%; as:0.006%; sb:0.002%; pb:0.003%; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 800 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1080 ℃, and the tempering temperature is 760 ℃.
Example 3
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.082%; si:0.31 percent; mn:0.32 percent; p:0.010%; s:0.005 percent; : cr:9.22 percent; : mo:0.91 percent; v:0.23 percent; n:0.059%; nb:0.086%; ni:0.35 percent; al:0.017 percent; ti:0.007%; zr:0.003%; cu:0.06 percent; sn:0.002%; as:0.005 percent; sb:0.002%; pb:0.005 percent; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 860 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1060 ℃, and the tempering temperature is 770 ℃.
Example 4
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.085%; si:0.39 percent; mn:0.52 percent; p:0.018%; s:0.003%; : cr:9.42 percent; : mo:0.98 percent; v:0.21 percent; n:0.060%; nb:0.072%; ni:0.32 percent; al:0.016 percent; ti:0.005 percent; zr:0.003%; cu:0.06 percent; sn:0.002%; as:0.006%; sb:0.002%; pb:0.003%; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 810 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1040 ℃, and the tempering temperature is 750 ℃.
Example 5
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.097%; si:0.38 percent; mn:0.52 percent; p:0.011 percent; s:0.003%; : cr:9.46 percent; : mo:0.95 percent; v:0.21 percent; n:0.062%; nb:0.062%; ni:0.32 percent; al:0.016 percent; ti:0.003%; zr:0.006%; cu:0.06 percent; sn:0.002%; as:0.005 percent; sb:0.002%; pb:0.003%; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 860 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1080 ℃, and the tempering temperature is 750 ℃.
Example 6
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in parts by weight:
c:0.098%; si:0.42 percent; mn:0.35 percent; p:0.018%; s:0.003%; : cr:9.36 percent; : mo:0.98 percent; v:0.23 percent; n:0.066%; nb:0.076%; ni:0.32 percent; al:0.015 percent; ti:0.007%; zr:0.003%; cu:0.05 percent; sn:0.002%; as:0.006%; sb:0.002%; pb:0.005 percent; bi:0.003% of iron and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 820 ℃, a steel ingot riser is removed by 15 percent, a water gap is removed by 5 percent, the normalizing heating temperature is 1080 ℃ and the tempering temperature is 760 ℃.
Comparative example 1 (patented chemical composition, conventional forging and heat treatment process, which may prove effective)
An F91 alloy steel forging for a fast reactor nuclear power station comprises the following components in percentage by weight:
c:0.097%; si:0.38 percent; mn:0.52 percent; p:0.011 percent; s:0.003%; : cr:9.46 percent; : mo:0.95 percent; v:0.21 percent; n:0.062%; nb:0.062%; ni:0.32 percent; al:0.016 percent; ti:0.003%; zr:0.006%; cu:0.06 percent; sn:0.002%; as:0.005 percent; sb:0.002%; pb:0.003%; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1230 ℃, the final forging temperature is 780 ℃, the riser of the steel ingot is removed by 10 percent, the water gap is removed by 5 percent, the normalizing heating temperature is 1020 ℃, and the tempering temperature is 720 ℃.
Comparative example 2 (traditional chemical composition, patented forging process, traditional heat treatment process, can prove patented forging process effective)
C:0.082%; si:0.31 percent; mn:0.32 percent; p:0.015 percent; s:0.006%; : cr:8.26 percent; : mo:0.86 percent; v:0.19 percent; n:0.059%; nb:0.086%; ni:0.35 percent; al:0.017 percent; ti:0.007%; zr:0.003%; cu:0.06 percent; sn:0.002%; as:0.005 percent; sb:0.002%; pb:0.005 percent; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1220 ℃, the final forging temperature is 850 ℃, the riser of the steel ingot is removed by 15 percent, the nozzle is removed by 5 percent, the normalizing heating temperature is 1020 ℃, and the tempering temperature is 720 ℃.
Comparative example 3 (traditional chemical composition, traditional forging process, patented heat treatment process, which may prove effective)
C:0.086%; si:0.36 percent; mn:0.39 percent; p:0.016 percent; s:0.005 percent; : cr:8.22 percent; : mo:0.86 percent; v:0.18 percent; n:0.058%; nb:0.082%; ni:0.32 percent; al:0.017 percent; ti:0.006%; zr:0.002%; cu:0.05 percent; sn:0.002%; as:0.003%; sb:0.002%; pb:0.003%; bi:0.005% and the balance of iron.
In the production process, the initial forging temperature is 1230 ℃, the final forging temperature is 780 ℃, the riser of the steel ingot is removed by 10 percent, the water gap is removed by 5 percent, the normalizing heating temperature is 1060 ℃, and the tempering temperature is 760 ℃.
Mechanical property test:
the compositions and process methods of the present application were tested for performance, room temperature tensile, impact, and brinell hardness tests were performed as specified in ASTM a 370; the high temperature tensile test was performed as specified in ASTM E21.
The tensile specimen is preferably a circular specimen having a diameter of 12.5mm and a gauge length of 50mm, which when not intercepted, allows the specimens of other dimensions specified in ASTM a370 to be intercepted.
The impact sample adopts a standard sample; when the nominal wall thickness of the steel pipe connected with the forge piece is less than or equal to 16mm, the impact sample can not be intercepted.
Surface-dynamic performance
TABLE II impact test (Unit: J)
Endurance strength test
The permanent strength test is used to evaluate material properties at long-term operating temperatures. The heat treatment state of the sample is a post-weld simulated heat treatment state added to delivery.
The endurance strength tests are respectively carried out at 500 ℃, 525 ℃ and 550 ℃, and the stress load and the target fracture time meet the third specification.
TABLE III permanent Strength requirement
The permanent strength test was carried out as specified in ASTM E139. The results are shown in the following table:
TABLE IV PERSISTENT STRENGTH TEST
The above description is only an embodiment of the present invention, and not intended to limit the scope of the present invention, and all modifications of equivalent structures and equivalent processes, which are made by the present specification, or directly or indirectly applied to other related technical fields, are included in the scope of the present invention.
Claims (9)
1. The F91 alloy steel forging for the fast reactor nuclear power station is characterized by comprising the following components in percentage by weight:
c is between 0.08 and 0.12 percent; si is more than or equal to 0.20 percent and less than or equal to 0.50 percent; mn is more than or equal to 0.30 percent and less than or equal to 0.60 percent; p is less than or equal to 0.020%; s is less than or equal to 0.010 percent; cr is more than or equal to 9.00 percent and less than or equal to 9.50 percent; mo is more than or equal to 0.90 percent and less than or equal to 1.05 percent; v is more than or equal to 0.20 percent and less than or equal to 0.25 percent; n is more than or equal to 0.030% and less than or equal to 0.070%; nb is more than or equal to 0.06 percent and less than or equal to 0.10 percent; ni is less than or equal to 0.40 percent; al is less than or equal to 0.02 percent; ti is less than or equal to 0.01 percent; zr is less than or equal to 0.01 percent; cu is less than or equal to 0.10 percent; sn is less than or equal to 0.005 percent; as is less than or equal to 0.010 percent; sb is less than or equal to 0.003 percent; pb is less than or equal to 0.008 percent; bi is less than or equal to 0.008 percent, and the balance is iron.
2. The F91 alloy steel forging for the fast reactor nuclear power station as claimed in claim 1, wherein (C + N) is not less than 0.12%.
3. The F91 alloy steel forging for the fast reactor nuclear power station as claimed in claim 1, wherein the ratio of N/Al is greater than or equal to 4.
4. The F91 alloy steel forging for the fast reactor nuclear power station As claimed in claim 1, wherein (As + Sn + Sb + Pb) is less than or equal to 0.020%.
5. The F91 alloy steel forging for the fast reactor nuclear power station As claimed in claim 1, wherein (As + Sn + Sb + Pb) is less than or equal to 0.015%.
6. A production process for the alloy steel forging of any one of claims 1 to 5, characterized by comprising the following steps:
s1, raw material refining: refining the raw materials outside an electric furnace into an alloy steel ingot containing the chemical components;
s2, forging: and forging the obtained alloy steel ingot into an alloy steel forging by using a press, wherein the total forging ratio of the forging is more than 3, the initial forging temperature is 1220 ℃, the final forging temperature is more than or equal to 800 ℃, the riser part of the steel ingot is removed by 15 percent, and the nozzle part of the steel ingot is removed by 5 percent.
S3, heat treatment: the heating temperature during normalizing or quenching is 1040-1080 ℃, and the tempering temperature is 750-780 ℃;
s4, detection: and performing performance detection and nondestructive detection on the alloy steel forging subjected to heat treatment.
7. The production process of the F91 alloy steel forging for the fast reactor nuclear power station as claimed in claim 6, wherein the press in S2 is a 3600 ton press.
8. The production process of the F91 alloy steel forging for the fast reactor nuclear power station as claimed in claim 6, wherein in S3, when the section thickness is more than 75mm during heat treatment, the heat treatment is quenching and tempering, the heating temperature during quenching is 1040-1080 ℃, and the tempering temperature is 750-780 ℃.
9. The production process of the F91 alloy steel forging for the fast reactor nuclear power station as claimed in claim 6, wherein the total forging ratio of the forging in S2 is greater than 4.5.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN110551943A (en) * | 2019-09-16 | 2019-12-10 | 无锡市法兰锻造有限公司 | 026Cr18Ni12Mo2N stainless steel forging for nuclear power station and manufacturing method thereof |
| CN114959456A (en) * | 2022-04-29 | 2022-08-30 | 江油市长祥特殊钢制造有限公司 | Nuclear power SA182F91 valve body and preparation method thereof |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN110551943A (en) * | 2019-09-16 | 2019-12-10 | 无锡市法兰锻造有限公司 | 026Cr18Ni12Mo2N stainless steel forging for nuclear power station and manufacturing method thereof |
| CN114959456A (en) * | 2022-04-29 | 2022-08-30 | 江油市长祥特殊钢制造有限公司 | Nuclear power SA182F91 valve body and preparation method thereof |
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