700℃时效对9Cr ODS钢微观组织和力学性能的影响
收稿日期: 2022-11-01
修回日期: 2022-12-11
网络出版日期: 2023-04-07
基金资助
国家重点研发计划项目(2018YFA0702900);国家自然科学基金项目(52173305);国家自然科学基金项目(52101061);国家自然科学基金项目(52233017);国家自然科学基金项目(52203384);中国博士后科学基金项目(2020M681004);中国博士后科学基金项目(2021M703276);中国科学院金属研究所创新基金项目(2022-PY12);中核集团领创项目;中国科学院青年创新促进会项目
Effect of Aging Treatment at 700oC on Microstructure and Mechanical Properties of 9Cr ODS Steel
Received date: 2022-11-01
Revised date: 2022-12-11
Online published: 2023-04-07
Supported by
National Key Research and Development Program of China(2018YFA0702900);National Natural Science Foundation of China(52173305);National Natural Science Foundation of China(52101061);National Natural Science Foundation of China(52233017);National Natural Science Foundation of China(52203384);China Postdoctoral Science Foundation(2020M681004);China Postdoctoral Science Foundation(2021M703276);IMR Innovation Foundation(2022-PY12);LingChuang Research Project of China National Nuclear Corporation;Youth Innovation Promotion Association, CAS
为探究近服役温度时效行为对ODS钢微观组织和力学性能的影响,通过SEM、TEM和拉伸性能测试等方法,研究了9Cr ODS钢在700℃时效不同时间后的碳化物(M23C6)、纳米氧化物演变和力学性能变化。结果表明:在时效初期(≤ 200 h),M23C6在晶界处呈条带状快速析出并聚集长大,纳米氧化物无明显变化;在时效中期(200和1000 h),M23C6和纳米氧化物稳定长大;在时效后期(2000和3000 h),M23C6达到亚微米级,纳米氧化物的平均尺寸和数密度趋于稳定,与初始态相比,其平均尺寸的增长率为19.7%,数密度的下降率为27.1%。因纳米氧化物对不断增殖位错的钉扎,在部分晶粒内出现了位错胞和回复亚晶。9Cr ODS钢的拉伸强度在时效初期快速下降。在时效中后期,虽然纳米氧化物平均尺寸增加、数密度降低,但其钉扎作用仍然显著,以及基体中不断增殖的位错使得材料的拉伸强度维持稳定,延伸率在时效1000和2000 h期间处于低谷。
汪建强 , 刘威峰 , 刘生 , 徐斌 , 孙明月 , 李殿中 . 700℃时效对9Cr ODS钢微观组织和力学性能的影响[J]. 金属学报, 2024 , 60(5) : 616 -626 . DOI: 10.11900/0412.1961.2022.00558
Compared to second- and third-generation nuclear power systems, the Generation IV fission and future fusion reactors have higher service temperatures and irradiation doses, as well as harsher corrosive conditions and complex alternating loads. The structural materials for advanced reactors need to be researched and developed further. The oxide dispersion strengthened (ODS) steel has excellent high-temperature performance and irradiation resistance and is considered a promising structural material for advanced nuclear power systems. To reveal the effect of aging on microstructure and mechanical properties of ODS steel at near-service temperatures, the evolution of carbide M23C6 and nano-oxide particles (NPs) as well as the changes in the mechanical properties of 9Cr ODS steel after aging at 700oC for varying durations were studied using SEM, TEM, and tensile testing. M23C6 rapidly precipitated along grain boundaries, gradually aggregated, and grew during early aging (≤ 200 h). While the NPs showed no noticeable change. During the midstages of aging (200 and 1000 h), NPs and carbides grew stably. In the later stages of aging (2000 and 3000 h), carbide particles grew to the micron scale. The average size and number density of the NPs tended to be stable. Compared to the initial 9Cr ODS steel, the growth rate of the average size was 19.7%, and the reduction rate of the number density was 27.1%. Dislocation cells and recovered subgrains appeared within some grains because of the pinning effect of NPs on continuous proliferation dislocations. The tensile strength rapidly decreased at the initial stages of aging. In the intermediate and later stages of aging, although the average size of the NPs increased and the number density decreased, its pinning effect was still prominent. Continuous proliferation dislocations were observed in the matrix, so the tensile strength remained stable. Furthermore, the tensile elongation was low during aging time of 1000 and 2000 h.
Key words: 9Cr ODS steel; aging; carbide; nano-oxide particle; mechanical property
| 1 | Liu C L. Development status and trend of global nuclear power[J]. Global Sci., Technol. Econ. Outlook, 2017, 32(5): 67 |
| 刘春龙. 全球核电发展现状及趋势[J]. 全球科技经济瞭望, 2017, 32(5): 67 | |
| 2 | Rong J, Liu Z. Development and prospect of advanced nuclear energy technology[J]. At. Energy Sci. Technol., 2020, 54: 1638 |
| 荣 健, 刘 展. 先进核能技术发展与展望[J]. 原子能科学技术, 2020, 54: 1638 | |
| 3 | Zinkle S J, Was G S. Materials challenges in nuclear energy[J]. Acta Mater., 2013, 61: 735 |
| 4 | Abram T, Ion S. Generation-IV nuclear power: A review of the state of the science[J]. Energy Policy, 2008, 36: 4323 |
| 5 | Murty K L, Charit I. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities[J]. J. Nucl. Mater., 2008, 383: 189 |
| 6 | Kurtz R J, Odette G R. Structural Alloys for Nuclear Energy Applications[M]. Amsterdam: Elsevier, 2019: 51 |
| 7 | Zinkle S J, Boutard J L, Hoelzer D T, et al. Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications[J]. Nucl. Fusion, 2017, 57: 092005 |
| 8 | Massey C P, Hoelzer D T, Edmondson P D, et al. Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep[J]. Scr. Mater., 2019, 170: 134 |
| 9 | Stan T, Wu Y, Ciston J, et al. Characterization of polyhedral nano-oxides and helium bubbles in an annealed nanostructured ferritic alloy[J]. Acta Mater., 2020, 183: 484 |
| 10 | Odette G R. Recent progress in developing and qualifying nanostructured ferritic alloys for advanced fission and fusion applications[J]. JOM, 2014, 66: 2427 |
| 11 | Yvon P, Le Flem M, Cabet C, et al. Structural materials for next generation nuclear systems: challenges and the path forward[J]. Nucl. Eng. Des., 2015, 294: 161 |
| 12 | Ukai S, Ohtsuka S, Kaito K, et al. Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors[A]. Structural Materials for Generation IV Nuclear Reactors[M]. Amsterdam: Woodhead Publishing, 2017: 357 |
| 13 | Peng Y Y, Yu L M, Liu Y C, et al. Effect of ageing treatment at 650oC on microstructure and properties of 9Cr-ODS steel[J]. Acta Metall. Sin., 2020, 56: 1075 |
| 彭艳艳, 余黎明, 刘永长 等. 650℃时效对9Cr-ODS钢显微组织和性能的影响[J]. 金属学报, 2020, 56: 1075 | |
| 14 | Zhang G M, Zhou Z J, Mo K, et al. The effect of thermal-aging on the microstructure and mechanical properties of 9Cr ferritic/martensitic ODS alloy[J]. J. Nucl. Mater., 2019, 522: 212 |
| 15 | Li S F, Zhou Z J, Wang P H, et al. Long-term thermal-aging stability of a 16Cr-oxide dispersion strengthened ferritic steel at 973 K[J]. Mater. Design, 2016, 90: 318 |
| 16 | Oksiuta Z, Lewandowska M, Kurzyd?owski K J. Mechanical properties and thermal stability of nanostructured ODS RAF steels[J]. Mech. Mater., 2013, 67: 15 |
| 17 | Zilnyk K D, Pradeep K G, Choi P, et al. Long-term thermal stability of nanoclusters in ODS-Eurofer steel: An atom probe tomography study[J]. J. Nucl. Mater., 2017, 492: 142 |
| 18 | Sandim M J R, Filho I R S, Bredda E H, et al. Short communication on “Coarsening of Y-rich oxide particles in 9%Cr-ODS Eurofer steel annealed at 1350oC”[J]. J. Nucl. Mater., 2017, 484: 283 |
| 19 | Renzetti R A, Sandim H R Z, Sandim M J R, et al. Annealing effects on microstructure and coercive field of ferritic-martensitic ODS Eurofer steel[J]. Mater. Sci. Eng., 2011, A528: 1442 |
| 20 | Cunningham N, Wu Y, Klingensmith D, et al. On the remarkable thermal stability of nanostructured ferritic alloys[J]. Mater. Sci. Eng., 2014, A613: 296 |
| 21 | Zinkle S J, Snead L L. Designing radiation resistance in materials for fusion energy[J]. Annu. Rev. Mater. Res., 2014, 44: 241 |
| 22 | Zinkle S J. Challenges in developing materials for fusion technology—Past, present and future[J]. Fusion Sci. Technol., 2013, 64: 65 |
| 23 | Wang J Q, Liu S, Xu B, et al. Microstructural stability of a 9Cr oxide dispersion strengthened alloy under thermal aging at high temperatures[J]. J. Alloys Compd., 2023, 932: 167691 |
| 24 | Yakel H L. Atom distributions in tau-carbide phases: Fe and Cr distributions in (Cr23 - x Fe x )C6 with x = 0, 0.74, 1.70, 4.13 and 7.36[J]. Acta Crystallogr. Sect., 1987, 43B: 230 |
| 25 | Becker K, Ebert F. Die kristallstruktur einiger bin?rer carbide und nitride[J]. Z. Physik, 1925, 31: 268 |
| 26 | Godec M, Skobir Balanti? D A. Coarsening behaviour of M23C6 carbides in creep-resistant steel exposed to high temperatures[J]. Sci. Rep., 2016, 6: 29734 |
| 27 | Baltu?nikas A, Gryb?nas A, Kriūkien? R, et al. Evolution of crystallographic structure of M23C6 carbide under thermal aging of P91 steel[J]. J. Mater. Eng. Perform., 2019, 28: 1480 |
| 28 | Liu X, Miao Y B, Li M M, et al. Radiation resistance of oxide dispersion strengthened alloys: Perspectives from in situ observations and rate theory calculations[J]. Scr. Mater., 2018, 148: 33 |
| 29 | Miller M K, Hoelzer D T, Kenik E A, et al. Stability of ferritic MA/ODS alloys at high temperatures[J]. Intermetallics, 2015, 13: 387 |
| 30 | Chen L Z, Li S F, Liao L, et al. Microstructure, tensile properties and thermal stability of 14Cr-ODS steel[J]. Trans. Mater. Heat Treat., 2019, 40(11): 124 |
| 陈灵芝, 李少夫, 廖 璐 等. 14Cr-ODS钢的显微组织和拉伸性能及热稳定性[J]. 材料热处理学报, 2019, 40(11): 124 | |
| 31 | Zhang Z P, Shi Q Z, Zhao Q, et al. Thermal aging behavior of 14Cr-ODS steel[J]. Trans. Mater. Heat Treat., 2020, 45(6): 153 |
| 张哲平, 史庆志, 赵 倩 等. 14Cr-ODS钢的热时效行为[J]. 材料热处理学报, 2020, 45(6): 153 | |
| 32 | Wang H, Yan W, van Zwaag S, et al. On the 650oC thermostability of 9-12Cr heat resistant steels containing different precipitates[J]. Acta Mater., 2017, 134: 143 |
| 33 | Abe F, Araki H, Noda T. The effect of tungsten on dislocation recovery and precipitation behavior of low-activation martensitic 9Cr steels[J]. Metall. Trans., 1991, 22A: 2225 |
| 34 | Miller M K, Hoelzer D T, Kenik E A, et al. Nanometer scale precipitation in ferritic MA/ODS alloy MA957[J]. J. Nucl. Mater., 2004, 329-333: 338 |
| 35 | Zheng P F, Li Y F, Zhang J R, et al. On the thermal stability of a 9Cr-ODS steel aged at 700oC up to 10000 h mechanical properties and microstructure[J]. Mater. Sci. Eng., 2020, A783: 139292 |
| 36 | Abe F. Precipitate design for creep strengthening of 9%Cr tempered martensitic steel for ultra-supercritical power plants[J]. Sci. Technol. Adv. Mater., 2008, 9: 013002 |
| 37 | Ramar A, Sp?tig P, Sch?ublin R. Analysis of high temperature deformation mechanism in ODS EUROFER97 alloy[J]. J. Nucl. Mater., 2008, 382: 210 |
| 38 | Primig S, Leitner H, Knabl W, et al. Textural evolution during dynamic recovery and static recrystallization of molybdenum[J]. Metall. Mater. Trans., 2012, 43A: 4794 |
/
| 〈 |
|
〉 |