基于微结构演化的RAFM钢中子辐照硬化/脆化模型研究

朱霄汉; 李孝晨; 郑明杰

基于微结构演化的RAFM钢中子辐照硬化/脆化模型研究

朱霄汉^1,2,
李孝晨^1,2,
郑明杰^1,2, ,

1. 中国科学院合肥物质科学研究院;
2. 中国科学技术大学

基金项目:

中科院国际伙伴计划全球共性挑战专项(145GJHZ2022055GC)

中国科学院特别交流计划A(2022000216)

中国科学院合肥物质科学研究院院长基金国际合作探索项目(2021YZGH05)

详细信息

作者简介:
朱霄汉(1993—),男,安徽合肥人,博士,现从事结构材料辐照效应方面研究

通讯作者:
郑明杰,E-mail:mingjie.zheng@inest.cas.cn

中图分类号: TL341
计量
- 文章访问数: 0
- HTML全文浏览量: 0
- PDF下载量: 0
出版历程
- 收稿日期: 2022-04-27
- 刊出日期: 2024-06-27

Modeling on Irradiation Hardening/embrittlement of RAFM Steel Based on Microstructure Evolution

1. Hefei Institutes of Physical Science, Chinese Academy of Sciences;
2. University of Science and Technology of China

摘要

摘要: 低活化铁素体/马氏体钢(RAFM)作为聚变堆的重要候选结构材料之一，在中子辐照下，会产生硬化/脆化等辐照损伤行为，影响其服役安全性。发展基于微结构演化的辐照硬化/脆化模型是研究该问题的重要手段。本工作通过建立包含经典硬化模型与速率理论的耦合模型，描述了辐照条件下材料缺陷微结构演化对辐照硬化/脆化的影响。利用该耦合模型，以中国低活化马氏体钢(CLAM)为例计算了其在中子辐照条件下(0～22 dpa)屈服强度与剂量和温度的关系。结果表明，RAFM钢辐照硬化的峰值温度约为300℃。在峰值温度下，辐照剂量达22 dpa时RAFM钢的屈服强度增量超过500 MPa。分析了辐照产生的位错环、空洞及氦泡对辐照硬化的贡献，其中位错环导致的辐照硬化占比超过80%。并预测了在300℃、0～22 dpa剂量范围内RAFM钢的显微硬度和韧脆转变温度(DBTT)的变化。综合结果分析，位错环是辐照硬化/脆化效应最主要的影响因素。
- RAFM钢 /
- 中子辐照硬化/脆化 /
- 微结构演化 /
- 速率理论
Abstract: Reduced-activation ferritic/martensitic（RAFM） steel is the primary candidate structural material for fusion reactors and will face inevitable irradiation hardening/embrittlement under high-dose irradiation. Building the model for irradiation hardening/embrittlement based on microstructure evolution is a significant way to predict the performance of materials. In this work, a coupled model contains rate theory and strengthening model was developed. In the coupled model, the microstructure evolution under irradiation was related to the changes of mechanical properties. The irradiation hardening/embrittlement of China Low Activation Martensitic（CLAM） steel in the dose range 0～22 dpa was calculated. The irradiation hardening reaches a peak at about 300 ℃, and the increment of yield strength exceeds 500 MPa after 22 dpa. The contribution of different types of defects caused by irradiation to the increasement of strength is analyzed. Among them, the hardening caused by the dislocation loop is the highest, accounting for more than 80%. Combining the theoretical model and correlation factors, the changes in Vickers hardness and DBTT of RAFM steel under irradiation are predicted. From the results, the dislocation loop is the major reason that causing the irradiation hardening.
- RAFM steel /
- Irradiation hardening/embrittlement /
- Microstructure evolution /
- Rate theory

HTML全文

参考文献(31)

[1]	Muroga T,Gasparotto M,Zinkle S J.Overview of materials research for fusion reactors [J].Fusion Engineering and Design,2002,61-62:13-25.
[2]	Lucon E.Mechanical properties of the European reference RAFM steel (EUROFER-97) before and after irradiation at 300 C (0.3-2 dpa) [J].SCK· CEN report,BLG-962,2003.
[3]	Peng L,Ge H,Dai Y,et al.Microstructure and microhar dness of CLAM steel irradiated up to 20.8 ádpa in STIP-V [J].Journal of Nuclear Materials,2016,468:255-9.
[4]	Ge H,Peng L,Dai Y,et al.Tensile properties of CLAM steel irradiated up to 20.1 dpa in STIP-V [J].Journal of Nuclear Materials,2016,468:240-5.
[5]	Mansur L K,Grossbeck M L.Mechanical property changes induced in structural alloys by neutron irradiations with different helium to displacement ratios [J].Journal of Nuclear Materials,1988,155-157:130-47.
[6]	Dubinko V I,Kotrechko S A,Klepikov V F.Irradiation hardening of reactor pressure vessel steels due to the dislocation loop evolution [J].Radiation Effects and Defects in Solids,2009,164(10):647-55.
[7]	Wang C,Zhang C,Zhao J,et al.Microstructure evolution and yield strength of CLAM steel in low irradiation condition [J].Materials Science and Engineering:A,2017,682:563-8.
[8]	Yu Y,He X,Luo F,et al.Rate theory modeling of dislocation loops in RAFM steel under helium ion irradiation and comparison with experiments[J].Computational Materials Science,2015,110:34-8.
[9]	Morito S,Yoshida H,Maki T,et al.Effect of block size on the strength of lath martensite in low carbon steels [J].Materials Science and Engineering:A,2006,438:237-40.
[10]	Nabarro F.Dislocations in a simple cubic lattice [J].Proceedings of the Physical Society (1926—1948),1947,59(2):256.
[11]	Li X,Schönecker S,Simon E,et al.Tensile strain-induced softening of iron at high temperature [J].Scientific reports,2015,5(1):1-7.
[12]	Bacon D J,Kocks U F,Scattergood R O.The effect of dislocation self-interaction on the orowan stress [J].Philosophical Magazine,1973,28(6):1241-63.
[13]	Queyreau S,Monnet G,Devincre B.Orowan strengthening and forest hardening superposition examined by dislocation dynamics simulations [J].Acta Materialia,2010,58(17):5586-95.
[14]	Dadé M,Malaplate J,Garnier J,et al.Influence of microstructural parameters on the mechanical properties of oxide dispersion strengthened Fe-14Cr steels [J].Acta Materialia,2017,127:165-77.
[15]	Mecking H,Kocks U.Kinetics of flow and strain-harden ing [J].Acta metallurgica,1981,29(11):1865-75.
[16]	Bullough R,Eyre B,Krishan K.Cascade damage effects on the swelling of irradiated materials [J].Proceedings of the Royal Society of London A Mathematical and Physical Sciences,1975,346(1644):81-102.
[17]	Zhu X,Li X,Zheng M.Predicting the Irradiation Swelling of Austenitic and Ferritic/Martensitic Steels,Based on the Coupled Model of Machine Learning and Rate Theory [J].Metals,2022,12(4):651.
[18]	Brimbal D,Fournier L,Barbu A.Cluster dynamics modeling of the effect of high dose irradiation and helium on the microstructure of austenitic stainless steels [J].Journal of Nuclear Materials,2016,468:124-39.
[19]	Hashimoto N,Sakuraya S,Tanimoto J,et al.Effect of impurities on vacancy migration energy in Fe-based alloys [J].Journal of Nuclear Materials,2014,445(1):224-6.
[20]	Tan L,Snead L L,Katoh Y.Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors [J].Journal of Nuclear Materials,2016,478:42-9.
[21]	Wu Y,Li C,Xia X,et al.Precipitate coarsening and its effects on the hot deformation behavior of the recently developed γ′-strengthened superalloys[J].Journal of Materials Science & Technology,2021,67:95-104.
[22]	Yamamoto T,Odette G R,Kishimoto H,et al.On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of-8Cr tempered martensitic steels:Compilation and analysis of existing data [J].Journal of nuclear materials,2006,356(1-3):27-49.
[23]	Tabor D.The physical meaning of indentation and scratch hardness [J].British Journal of Applied Physics,1956,7(5):159.
[24]	Busby J T,Hash M C,Was G S.The relationship between hardness and yield stress in irradiated austenitic and ferritic steels [J].Journal of Nuclear Materials,2005,336(2-3):267-78.
[25]	葛洪恩.CLAM钢中子辐照硬化行为研究 [D].安徽:中国科学技术大学,2015.
[26]	Materna-Morris E,Schneider H C,Möslang A.Tensile behavior of RAFM alloys after neutron irradiation of up to 16.3dpa between 250 and 450 ℃ [J].Journal of Nuclear Materials,2014,455(1):728-34.
[27]	Gaganidze E,Aktaa J.Assessment of neutron irradiation effects on RAFM steels [J].Fusion Engineering and Design,2013,88(3):118-28.
[28]	Lucon E,Chaouadi R,Decréton M.Mechanical properties of the European reference RAFM steel (EUROFER97) before and after irradiation at 300 ℃ [J].Journal of nuclear materials,2004,329:1078-82.
[29]	Higgy H,Hammad F.Effect of fast-neutron irradiation on mechanical properties of stainless steels:AISI types 304,316 and 347 [J].Journal of Nuclear Materials,1975,55(2):177-86.
[30]	Odette G,Lucas G.The effects of intermediate temperature irradiation on the mechanical behavior of 300-series austenitic stainless steels [J].Journal of nuclear materials,1991,179:572-6.
[31]	Grossbeck M,Maziasz P,Rowcliffe A.Modeling of strengthening mechanisms in irradiated fusion reactor first wall alloys [J].Journal of nuclear materials,1992,191:808-12.