CN103820705B - The nuclear power container property heat treatment method of SA508-3 heavy froging - Google Patents
The nuclear power container property heat treatment method of SA508-3 heavy froging Download PDFInfo
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- CN103820705B CN103820705B CN201210468761.0A CN201210468761A CN103820705B CN 103820705 B CN103820705 B CN 103820705B CN 201210468761 A CN201210468761 A CN 201210468761A CN 103820705 B CN103820705 B CN 103820705B
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Abstract
The invention discloses the property heat treatment method of a kind of nuclear power container SA508-3 heavy froging, for being SA508-3 to material, external diameter is 3.5 ~ 6.5m, be highly no more than 5m, nuclear power container forging that wall thickness is 100 ~ 250mm carries out property heat treatment, comprise the following steps: the first step, first time quenching; Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature; Second step, second time quenching; 3rd step, tempering; 4 ~ 5 hours are incubated, air cooling of coming out of the stove after forging is heated to 635 ~ 660 DEG C with the heat-up rate of≤100 DEG C/h.The present invention adopts repeated hardening to operate before high tempering, by repeated hardening thinning microstructure, obtain desired properties eventually through tempering adjustment, can on the basis that proof strength is qualified, promote nuclear power heavy froging low-temperature flexibility, thus meet the performance requriements of nuclear power heavy froging.
Description
Technical field
The present invention relates to a kind of heat treating method, be specifically related to the property heat treatment method of a kind of nuclear power container SA508-3 heavy froging.
Background technology
Core couple capacitors ensures that Nuclear power plants plays vital effect in the whole safe operation reached in the military service cycle of 40 ~ 60 years, therefore nuclear power container generally adopts high performance heavy froging assembly welding to form.
Nuclear power container SA508-3 heavy froging general requirement is as follows:
1, have higher room temperature strength and hot strength, this technical indicator is recorded by tensile test at room temperature and high temperature tension test;
2, have enough toughness, especially low-temperature flexibility, this technical indicator is generally recorded by Charpy impact test or drop weight test.From security standpoint, general requirement, on the basis of proof strength, should improve the toughness of forging material as far as possible.
Along with the continuous evolution of nuclear power technology, the safety margin of nuclear power increases, and life extends, and also day by day improves the performance requriements of nuclear power container heavy froging, as shown in table 1:
Table 1
In table 1, Rp0.2 is yield strength, and Rm is tensile strength, and Kv is Charpy-V impact power, RT
nDTit is zero ductility transition temperature.
As can be seen from Table 1, along with the evolution of nuclear power type, for the third generation pressurized-water reactor AP1000 nuclear power evaporator forging of current main flow, while low intensity limit requires to be increased to 620MPa, low-temperature flexibility performance assessment criteria zero ductility transition temperature RT
nDTfrom two generations≤-10 DEG C be promoted to≤-21 DEG C, the obdurability of forging requires to improve a lot, and has higher requirement to the heat treatment technics of forging.
Compressed water reactor nuclear power container forging adopts SA508-3 (or quite steel grade, 18MND5 and 16MND5 as the French trade mark) steel of ASME standard.SA508-3 belongs to typical Mn-Ni-Mo low alloy steel, because alloy content is few, only has limited hardening capacity, belongs to typical bainitic steel.Generally speaking, for improving the hardening capacity of material as far as possible, the actual alloying constituent (being mainly Mn, Ni, Mo) of SA508-3 steel is controlled the upper limit allowed at regulating scope by manufactory.SA508-3 material structure and performance and quenching cooling rate in close relations, generally speaking, cooling rate is faster, the more over-all properties of energy acquisition preferably lower bainite organizes even martensitic stucture, therefore the manufacturing concern of nuclear power heavy froging unanimously puts forth effort on quickening quenching cooling rate to meet more and more higher performance requriements.But be subject to the restriction of technical capacity, under Practical Project condition, the heavy froging of SA508-3 steel is difficult to obtain lower bainite tissue.
The thermal treatment to nuclear power heavy froging of nuclear material standard, specification proposes the control overflow of some directiveness, as ASMESA-508 standard specifies: forging should be heated to the temperature producing austenite structure, then in suitable fluid medium, spray or immersed method are quenched.RCC-M standard specifies: forging carries out 850 ~ 925 DEG C of scope austenitizings, then dip quench.The restriction of visible RCC-M to property heat treatment is more.The principle that heavy froging manufacturing concern generally formulates according to above-mentioned standard clause formulates concrete property heat treatment technique, i.e. 850 ~ 925 DEG C of scope austenitizings, then carry out being transferred to tank Cooling Quenching, after cooling terminates, carry out high tempering to obtain desired properties.
Adopt the thermal treatment process of the quenching+high tempering of above-mentioned routine, the performance requriements of most of nuclear power heavy froging can be met, but the defect still having part forging to bring due to front road technique (as composition is not good, segregation is more serious), in toughness after the property heat treatment of routine lower than code requirement.For these forging, must develop new thermal treatment process, further excavated material performance potential, just likely meets the performance requriements of forging.
Summary of the invention
Technical problem to be solved by this invention is to provide the property heat treatment method of a kind of nuclear power container SA508-3 heavy froging, and it can improve the obdurability of nuclear power container heavy froging.
For solving the problems of the technologies described above, the technical solution of the property heat treatment method of nuclear power container SA508-3 of the present invention heavy froging is:
For being SA508-3 to material, external diameter is 3.5 ~ 6.5m, be highly no more than 5m, nuclear power container forging that wall thickness is 100 ~ 250mm carries out property heat treatment, comprises the following steps:
The first step, first time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
Second step, second time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
3rd step, third time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature.
4th step, tempering;
4 ~ 5 hours are incubated, air cooling of coming out of the stove after forging is heated to 635 ~ 660 DEG C with the heat-up rate of≤100 DEG C/h.
The technique effect that the present invention can reach is:
The present invention adopts repeated hardening to operate before high tempering, by repeated hardening thinning microstructure, obtain desired properties eventually through tempering adjustment, can on the basis that proof strength is qualified, promote nuclear power heavy froging low-temperature flexibility, thus meet the performance requriements of nuclear power heavy froging.
The present invention, through repeated hardening, makes forging material repeatedly pass through quick austenitizing and quench cooled, finally obtains fine grain structure, then after follow-up high tempering thermal treatment, owing to organizing comparatively thin, obdurability index is all significantly improved forging.Compared with the forging without conventional hardening and tempering process thermal treatment (primary quenching), the forging intensity that the present invention obtains, toughness index are all higher.
The present invention successfully can promote the obdurability level of SA508-3 material, especially front road technique (as smelted, forging) existing defects is caused adopting conventional hardening and tempering process to be difficult to qualified forging, adopt heat treating method of the present invention, its intensity and toughness index can be improved simultaneously, meet the demand of technical standard of nuclear power heavy froging.
Below in conjunction with embodiment, the present invention is further detailed explanation:
Embodiment
The property heat treatment method of nuclear power container SA508-3 of the present invention heavy froging, for being SA508-3 to material, external diameter is 3.5 ~ 6.5m, be highly no more than 5m, nuclear power container forging that wall thickness is 100 ~ 250mm carries out property heat treatment, comprises the following steps:
The first step, first time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
Second step, second time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
3rd step, third time quenching;
If necessary, third time quenching is carried out;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
4th step, tempering;
4 ~ 5 hours are incubated, air cooling of coming out of the stove after forging is heated to 635 ~ 660 DEG C with the heat-up rate of≤100 DEG C/h.
Contrast through secondary circulation quenching and the nuclear power evaporator SA508-3 forging of three circulating quenchings and the prior art forging merely through primary quenching, result is as shown in table 2, table 3:
| Quenching times | Yield strength/MPa | Tensile strength/MPa | Elongation/% | Shrinking percentage/% |
| Examination value | ≥450 | 620～790 | ≥16 | ≥35 |
| Once | 515～520 | 650～660 | 20～22 | 62～68 |
| Twice | 525～540 | 660～680 | 20～21 | 68～70 |
| Three times | 560～570 | 695～700 | 21～22 | 69～70 |
Table 2
| Quenching times | -20℃AKV/J | Side expansion/mm | Fiber rate/% |
| Examination value | ≥40 | / | / |
| Once | 70～110 | 1.2～1.3 | 40～45 |
| Twice | 90～140 | 1.3～1.6 | 45～62 |
| Three times | 150～220 | 1.6～2.3 | 65～90 |
Table 3
Comparing result shows, compared with the thermal treatment process (primary quenching) of prior art, along with the increase of quenching times, the intensity index of forging and toughness index all have obvious increase, and performance margin obviously increases.
Claims (2)
1. the nuclear power container property heat treatment method of SA508-3 heavy froging, it is characterized in that, for being SA508-3 to material, external diameter is 3.5 ~ 6.5m, be highly no more than 5m, nuclear power container forging that wall thickness is 100 ~ 250mm carries out property heat treatment, comprises the following steps:
The first step, first time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
Second step, second time quenching;
Forging is entered after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature;
3rd step, tempering;
4 ~ 5 hours are incubated, air cooling of coming out of the stove after forging is heated to 635 ~ 660 DEG C with the heat-up rate of≤100 DEG C/h.
2. the property heat treatment method of nuclear power container SA508-3 according to claim 1 heavy froging, it is characterized in that, implement third time quenching before 3rd step after described second step, method is: entered by forging after stove is heated to 600 ~ 700 DEG C and be incubated 4 ~ 5 hours; Then be heated to be incubated 4 ~ 5 hours between 880 ~ 920 DEG C with the heat-up rate of≤100 DEG C/h; Water-cooled of coming out of the stove afterwards is to room temperature.
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| CN105779707A (en) * | 2016-05-26 | 2016-07-20 | 镇江市经纬工程机械有限公司 | Thermal treatment method of cast eccentric shaft |
| CN106191389B (en) * | 2016-08-26 | 2018-11-16 | 上海交通大学 | A kind of two-step method tempering process improving nuclear power heavy forging impact flexibility |
| CN106929637A (en) * | 2017-03-01 | 2017-07-07 | 上海电气上重铸锻有限公司 | A kind of nuclear power evaporator Technology for Heating Processing of ellipse head forging |
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| CN113667799B (en) * | 2021-08-19 | 2023-04-07 | 海隆石油工业集团有限公司 | Heat treatment method for improving sulfur resistance of high-steel-grade sulfur-resistant drill pipe welding area |
| CN114277223B (en) * | 2021-12-28 | 2023-09-29 | 江阴市恒业锻造有限公司 | Heat treatment method for high-low temperature impact toughness 10Ni3MoVD steel forging |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100261664B1 (en) * | 1997-10-21 | 2000-07-15 | 이종훈 | Intercritical heat treatment process for toughness improvement of sa508 gr.3 steel |
| CN101805819A (en) * | 2010-04-22 | 2010-08-18 | 山西太钢不锈钢股份有限公司 | Hardening and tempering method of thick steel plates for pressure container |
| CN101906520A (en) * | 2009-06-02 | 2010-12-08 | 上海重型机器厂有限公司 | Heat-treatment technology method for lower end socket forge piece of nuclear power reactor pressure vessel |
| CN102392195A (en) * | 2011-12-15 | 2012-03-28 | 钢铁研究总院 | High-strength high-toughness nuclear power pressure vessel forging steel and its manufacturing method |
-
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Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR100261664B1 (en) * | 1997-10-21 | 2000-07-15 | 이종훈 | Intercritical heat treatment process for toughness improvement of sa508 gr.3 steel |
| US6264770B1 (en) * | 1997-10-21 | 2001-07-24 | Korea Atomic Energy Research Inst. | Intercritical heat treatment process for toughness improvement of SA 508 GR.3 steel |
| CN101906520A (en) * | 2009-06-02 | 2010-12-08 | 上海重型机器厂有限公司 | Heat-treatment technology method for lower end socket forge piece of nuclear power reactor pressure vessel |
| CN101805819A (en) * | 2010-04-22 | 2010-08-18 | 山西太钢不锈钢股份有限公司 | Hardening and tempering method of thick steel plates for pressure container |
| CN102392195A (en) * | 2011-12-15 | 2012-03-28 | 钢铁研究总院 | High-strength high-toughness nuclear power pressure vessel forging steel and its manufacturing method |
Non-Patent Citations (2)
| Title |
|---|
| SA508Gr.3钢锻件调质处理及质量控制;贾兴元;《一重技术》;20101231(第6期);第35-38页 * |
| 国外核反应堆压力容器用A508-3钢及其制造;马飞良;《大型铸锻件》;19901231(第4期);第35-46页 * |
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Effective date of registration: 20161130 Address after: 200245 Jiangchuan Road, Shanghai, No. 207, building 1800, No. Patentee after: Shanghai Electric Heavy Forging Co. Ltd. Patentee after: Shanghai Heavy Machines Plant Co., Ltd. Address before: 200245 Jiangchuan Road, Shanghai, No. 1800, No. Patentee before: Shanghai Heavy Machines Plant Co., Ltd. |