Radiation damage of ultrafine grained and nanocrystalline 304 austenitic stainless steel subjected to heavy ion irradiation

Jinyang Ni; Jin Li; Miao Song; Huayan Hu; Tongde Shen; Zhengli Zhang; Engang Fu; Shangkun Shen; Heda Bai; Xuesong Leng; Bowen Bai; Yifan Huang; Xiangli Liu

doi:10.1016/j.jmrt.2025.09.210

Radiation damage of ultrafine grained and nanocrystalline 304 austenitic stainless steel subjected to heavy ion irradiation

Jinyang Ni
, Jin Li^*
, Miao Song^*
, Huayan Hu
, Tongde Shen
, Zhengli Zhang
, Engang Fu
, Shangkun Shen
, Heda Bai
, Xuesong Leng
, Bowen Bai
, Yifan Huang
, Xiangli Liu^*

^*Corresponding author for this work

Harbin Institute of Technology (Shenzhen)
Research Institute of Physical Sciences in Special Environments, Harbin Institute of Technology Shenzhen
Shanghai Jiao Tong University
Yanshan University
Peking University

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

Oxide dispersion strengthened (ODS) steels with nanoscale structures have significant potential as advanced structural materials in modern nuclear reactors due to their enhanced irradiation resistance. This study investigates La-doped ultrafine-grained (UFG) and nanocrystalline (NC) 304 austenitic stainless steels (304SS), emphasizing their improved irradiation resistance resulting from grain refinement and the formation of La-rich nanoparticles along grain boundaries. Commercial coarse-grained (CG) 304SS was studied as a baseline for comparison. The materials were irradiated with 6 MeV Au ions at 500 °C, reaching a displacement damage level of 220 displacements per atom (dpa). Microstructural evolution post-irradiation was characterized using transmission electron microscopy (TEM) and X-ray diffraction (XRD). Additionally, nanoindentation tests were conducted to measure the nanohardness and modulus of both pristine and irradiated samples. Furthermore, detailed analysis of microstructural changes and elemental segregation induced by Au-ion irradiation was compared with previous results from Fe-ion irradiation under comparable conditions.

Original language	English
Pages (from-to)	3771-3782
Number of pages	12
Journal	Journal of Materials Research and Technology
Volume	39
DOIs	https://doi.org/10.1016/j.jmrt.2025.09.210
State	Published - 1 Nov 2025
Externally published	Yes

Keywords

Heavy-ion irradiation
Nanocrystalline material
Oxide dispersion strengthened steel
Radiation induced segregation
Sink strength

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10.1016/j.jmrt.2025.09.210

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@article{ee9a9e7621b7406dacfc8ed8a9494b5f,

title = "Radiation damage of ultrafine grained and nanocrystalline 304 austenitic stainless steel subjected to heavy ion irradiation",

abstract = "Oxide dispersion strengthened (ODS) steels with nanoscale structures have significant potential as advanced structural materials in modern nuclear reactors due to their enhanced irradiation resistance. This study investigates La-doped ultrafine-grained (UFG) and nanocrystalline (NC) 304 austenitic stainless steels (304SS), emphasizing their improved irradiation resistance resulting from grain refinement and the formation of La-rich nanoparticles along grain boundaries. Commercial coarse-grained (CG) 304SS was studied as a baseline for comparison. The materials were irradiated with 6 MeV Au ions at 500 °C, reaching a displacement damage level of 220 displacements per atom (dpa). Microstructural evolution post-irradiation was characterized using transmission electron microscopy (TEM) and X-ray diffraction (XRD). Additionally, nanoindentation tests were conducted to measure the nanohardness and modulus of both pristine and irradiated samples. Furthermore, detailed analysis of microstructural changes and elemental segregation induced by Au-ion irradiation was compared with previous results from Fe-ion irradiation under comparable conditions.",

keywords = "Heavy-ion irradiation, Nanocrystalline material, Oxide dispersion strengthened steel, Radiation induced segregation, Sink strength",

author = "Jinyang Ni and Jin Li and Miao Song and Huayan Hu and Tongde Shen and Zhengli Zhang and Engang Fu and Shangkun Shen and Heda Bai and Xuesong Leng and Bowen Bai and Yifan Huang and Xiangli Liu",

note = "Publisher Copyright: {\textcopyright} 2025 The Authors.",

year = "2025",

month = nov,

day = "1",

doi = "10.1016/j.jmrt.2025.09.210",

language = "英语",

volume = "39",

pages = "3771--3782",

journal = "Journal of Materials Research and Technology",

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TY - JOUR

T1 - Radiation damage of ultrafine grained and nanocrystalline 304 austenitic stainless steel subjected to heavy ion irradiation

AU - Ni, Jinyang

AU - Li, Jin

AU - Song, Miao

AU - Hu, Huayan

AU - Shen, Tongde

AU - Zhang, Zhengli

AU - Fu, Engang

AU - Shen, Shangkun

AU - Bai, Heda

AU - Leng, Xuesong

AU - Bai, Bowen

AU - Huang, Yifan

AU - Liu, Xiangli

PY - 2025/11/1

Y1 - 2025/11/1

N2 - Oxide dispersion strengthened (ODS) steels with nanoscale structures have significant potential as advanced structural materials in modern nuclear reactors due to their enhanced irradiation resistance. This study investigates La-doped ultrafine-grained (UFG) and nanocrystalline (NC) 304 austenitic stainless steels (304SS), emphasizing their improved irradiation resistance resulting from grain refinement and the formation of La-rich nanoparticles along grain boundaries. Commercial coarse-grained (CG) 304SS was studied as a baseline for comparison. The materials were irradiated with 6 MeV Au ions at 500 °C, reaching a displacement damage level of 220 displacements per atom (dpa). Microstructural evolution post-irradiation was characterized using transmission electron microscopy (TEM) and X-ray diffraction (XRD). Additionally, nanoindentation tests were conducted to measure the nanohardness and modulus of both pristine and irradiated samples. Furthermore, detailed analysis of microstructural changes and elemental segregation induced by Au-ion irradiation was compared with previous results from Fe-ion irradiation under comparable conditions.

AB - Oxide dispersion strengthened (ODS) steels with nanoscale structures have significant potential as advanced structural materials in modern nuclear reactors due to their enhanced irradiation resistance. This study investigates La-doped ultrafine-grained (UFG) and nanocrystalline (NC) 304 austenitic stainless steels (304SS), emphasizing their improved irradiation resistance resulting from grain refinement and the formation of La-rich nanoparticles along grain boundaries. Commercial coarse-grained (CG) 304SS was studied as a baseline for comparison. The materials were irradiated with 6 MeV Au ions at 500 °C, reaching a displacement damage level of 220 displacements per atom (dpa). Microstructural evolution post-irradiation was characterized using transmission electron microscopy (TEM) and X-ray diffraction (XRD). Additionally, nanoindentation tests were conducted to measure the nanohardness and modulus of both pristine and irradiated samples. Furthermore, detailed analysis of microstructural changes and elemental segregation induced by Au-ion irradiation was compared with previous results from Fe-ion irradiation under comparable conditions.

KW - Heavy-ion irradiation

KW - Nanocrystalline material

KW - Oxide dispersion strengthened steel

KW - Radiation induced segregation

KW - Sink strength

UR - https://www.scopus.com/pages/publications/105019175244

U2 - 10.1016/j.jmrt.2025.09.210

DO - 10.1016/j.jmrt.2025.09.210

M3 - 文章

AN - SCOPUS:105019175244

SN - 2238-7854

VL - 39

SP - 3771

EP - 3782

JO - Journal of Materials Research and Technology

JF - Journal of Materials Research and Technology

ER -

Radiation damage of ultrafine grained and nanocrystalline 304 austenitic stainless steel subjected to heavy ion irradiation

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Keywords

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