Study on the Microstructure and Nano-hardness Evolution of FeCrAl Alloy under Ion Irradiation

Pei Jingyuan; Chen Huan; Zhang Ruiqian

doi:10.13832/j.jnpe.2025.S1.0145

Volume 46 Issue S1

Jul. 2025

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2025 > 46(S1): 145-157

Pei Jingyuan, Chen Huan, Zhang Ruiqian. Study on the Microstructure and Nano-hardness Evolution of FeCrAl Alloy under Ion Irradiation[J]. Nuclear Power Engineering, 2025, 46(S1): 145-157. doi: 10.13832/j.jnpe.2025.S1.0145

Citation:

Pei Jingyuan, Chen Huan, Zhang Ruiqian. Study on the Microstructure and Nano-hardness Evolution of FeCrAl Alloy under Ion Irradiation[J]. Nuclear Power Engineering, 2025, 46(S1): 145-157. doi: 10.13832/j.jnpe.2025.S1.0145

Citation:

PDF( 75323 KB)

Study on the Microstructure and Nano-hardness Evolution of FeCrAl Alloy under Ion Irradiation

doi: 10.13832/j.jnpe.2025.S1.0145

National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2025-01-18
Rev Recd Date: 2025-03-20
Publish Date: 2025-07-09

Abstract

Abstract

As an important candidate material for accident-resistant core cladding, it is necessary to deeply understand the modification mechanism of FeCrAl alloy under irradiation conditions. Au⁺ ions were used to irradiate the new Fe13Cr4.5Al alloy at room temperature and400°C. The phase structure, surface texture orientation, defects before and after irradiation, precipitated phase, amorphization and other microstructure and microhardness of the surface region of FeCrAl stainless steel before and after irradiation were systematically characterized. The correlation behavior and damage mechanism of irradiation defects, precipitated phase and hardening effect of FeCrAl stainless steel under ion irradiation were analyzed. With the increase of irradiation dose from 5 dpa to 20 dpa, the dislocation induced by irradiation has a "point-loop-line" evolution process. The density of 1/2<111> increases with the increase of irradiation dose, and the hardness of FeCrAl alloy also increases synchronously and reaches saturation after irradiation. The dislocation loop plays a leading role in hardening.
- FeCrAl alloy,
- Ion irradiation,
- Dislocation loops,
- Nanohardness,
- Irradiation hardening

FullText(HTML)

References(13)

References

[1]	刘俊凯,张新虎,恽迪. 事故容错燃料包壳候选材料的研究现状及展望[J]. 材料导报,2018, 32(11): 1757-1778. doi: 10.11896/j.issn.1005-023X.2018.11.001
[2]	李紫祎,王晓敏,王凯,等. 耐事故燃料研发进展及技术发展趋势[J]. 核动力工程,2024, 45(5): 155-164.
[3]	邱国兴,韦旭立,缪德军,等. 核级FeCrAl包壳材料研究进展[J]. 钢铁研究学报,2022, 34(9): 884-894.
[4]	GAMBLE K A, BARANI T, PIZZOCRI D, et al. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions[J]. Journal of Nuclear Materials, 2017, 491: 55-66. doi: 10.1016/j.jnucmat.2017.04.039
[5]	SWEET R T, GEORGE N M, MALDONADO G I, et al. Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation[J]. Nuclear Engineering and Design, 2018, 328: 10-26. doi: 10.1016/j.nucengdes.2017.11.043
[6]	龙弟均,徐海波,孙永铎,等. FeCrAl-ODS钢的辐照位错环演变及其辐照硬化效应[J]. 粉末冶金工业,2024, 34(3): 28-33.
[7]	EDMONDSON P D, BRIGGS S A, YAMAMOTO Y, et al. Irradiation-enhanced α′ precipitation in model FeCrAl alloys[J]. Scripta Materialia, 2016, 116: 112-116. doi: 10.1016/j.scriptamat.2016.02.002
[8]	雷阳,张海生,毛建军,等. 中子辐照对耐事故燃料FeCrAl合金力学性能的影响研究[J]. 核动力工程,2022, 43(1): 97-101.
[9]	FIELD K G, HU X X, LITTRELL K C, et al. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys[J]. Journal of Nuclear Materials, 2015, 465: 746-755. doi: 10.1016/j.jnucmat.2015.06.023
[10]	CHEN C L, RICHTER A, KÖGLER R. The effect of dual Fe⁺/He⁺ ion beam irradiation on microstructural changes in FeCrAl ODS alloys[J]. Journal of Alloys & Compounds, 2014, 586(S1): S173-S179.
[11]	STOLLER R E, ZINKLE S J. On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials[J]. Journal of Nuclear Materials, 2000, 283-287: 349-352. doi: 10.1016/S0022-3115(00)00378-0
[12]	YANG Y T, ZHANG C H, DING Z N, et al. A correlation between micro- and nano-indentation on materials irradiated by high-energy heavy ions[J]. Journal of Nuclear Materials, 2018, 498: 129-136. doi: 10.1016/j.jnucmat.2017.10.025
[13]	ZHOU X, WANG H, GUO L P, et al. Effect of niobium content on irradiation microstructure and hardening in FeCrAl-based alloys[J]. Journal of Materials Science & Technology, 2021, 95: 181-192.