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Stability of nanoscale particles in Oxide-Dispersion-Strengthened (ODS) steels under extremely large and multi-directional deformation conditions

研究課題

研究課題/領域番号 23K13087
研究種目

若手研究

配分区分基金
審査区分 小区分14020:核融合学関連
研究機関核融合科学研究所

研究代表者

申 晶潔  核融合科学研究所, 研究部, 助教 (80824747)

研究期間 (年度) 2023-04-01 – 2026-03-31
研究課題ステータス 交付 (2023年度)
配分額 *注記
4,680千円 (直接経費: 3,600千円、間接経費: 1,080千円)
2025年度: 780千円 (直接経費: 600千円、間接経費: 180千円)
2024年度: 1,950千円 (直接経費: 1,500千円、間接経費: 450千円)
2023年度: 1,950千円 (直接経費: 1,500千円、間接経費: 450千円)
キーワードODS steel / Microstructure / Ion irradiation / Irradiation effects / ODS ferritic steel / nanoscale particles / formation mechanisms / thermal stability / large deformation
研究開始時の研究の概要

This research is to investigate formation behaviors and the stability of nanoscale oxide particles in the ODS ferritic steel after extremely large plastic deformation to reveal the formation mechanisms of oxide particles, optimize the process parameters and develop the stable oxide particles.

研究実績の概要

The as-fabricated oxide dispersion strengthened (ODS) ferritic steel was recrystallized after large plastic deformation and subsequent heat treatment. The microstructural evolution and hardness changes under single-beam (Fe ions) and dual-beam (Fe and He ions) irradiation up to a peak damage dose of 10.5 displacements per atom (dpa) at elevated temperatures were investigated to clarify the irradiation resistance. Results showed that size and number density of the oxide particles were slightly decreased after ion irradiation. Compared with single-beam irradiation, high density of helium bubbles was observed after dual-beam irradiation. Larger helium bubbles are trapped at the grain boundaries in the as-fabricated specimen, and the size of helium bubbles in the grains is almost the same for both as-fabricated and recrystallized specimens. Nanoindentation hardness was evidently not changed after both single-beam and dual-beam irradiation at 973 K, suggesting that helium bubbles did not significantly induce hardening at this condition.

現在までの達成度 (区分)
現在までの達成度 (区分)

3: やや遅れている

理由

In order to make the laboratory-scale ODS steel with a designed chemical composition, adjustment of machine time, such as large glove boxes, hot isostatic pressing etc., is necessary. Also, to control the concentration of the impurities in the fabrication process, specialized parts, high-purity raw materials and atmosphere control should be considered.

今後の研究の推進方策

The designed ODS steels are to be made with high-purity raw materials. The coarse Ti-enriched particles are expected to be reduced or controlled by changing the Ti concentration and impurities. Moreover, the behaviors of the oxide particles and Ti-enriched particles during fabrication process will be investigated, and the formation mechanisms and thermal stability after plastic deformation will be elucidated.

報告書

(1件)
  • 2023 実施状況報告書
  • 研究成果

    (6件)

すべて 2024 2023

すべて 雑誌論文 (1件) (うち国際共著 1件、 査読あり 1件) 学会発表 (5件) (うち国際学会 3件)

  • [雑誌論文] Evolution of interfacial microstructure and oxides of CLAM steel by hot compression bonding2024

    • 著者名/発表者名
      Bai Yunfei、Wang Jianqiang、Zhu Gaofan、Nagasaka Takuya、Shen Jingjie、Sun Mingyue、Huang Qunying
    • 雑誌名

      Materials Characterization

      巻: 210 ページ: 113848-113848

    • DOI

      10.1016/j.matchar.2024.113848

    • 関連する報告書
      2023 実施状況報告書
    • 査読あり / 国際共著
  • [学会発表] Effect of Defect Distribution Gradient on Nano-oxide Behavior in 12Cr-ODS Steels Irradiated with 2.8 MeV Fe2+ Ions2024

    • 著者名/発表者名
      Zideng Wang, Jingjie Shen, Huilong Yang, Sho Kano, Hiroaki Abe
    • 学会等名
      2024 Spring Meeting of The Japan Institute of Metals and Materials
    • 関連する報告書
      2023 実施状況報告書
  • [学会発表] Study of ion irradiation effects on oxide dispersion strengthened (ODS) ferritic steel2023

    • 著者名/発表者名
      Jingjie Shen, Kiyohiro Yabuuchi
    • 学会等名
      The 14th International Symposium of Advanced Energy Science
    • 関連する報告書
      2023 実施状況報告書
    • 国際学会
  • [学会発表] Ion irradiation effects of 12Cr ODS steel after a novel recrystallization process2023

    • 著者名/発表者名
      Jingjie Shen, Takeo Muroga, Kiyohiro Yabuuchi, Sho Kano, Hiroaki Abe
    • 学会等名
      2023 Fall Meeting of Atomic Energy Society of Japan
    • 関連する報告書
      2023 実施状況報告書
  • [学会発表] Ion irradiation effects on as-fabricated and recrystallized 12Cr ODS steel at 973 K2023

    • 著者名/発表者名
      Jingjie Shen, Kiyohiro Yabuuchi, Huilong Yang, Sho Kano, Hiroaki Abe
    • 学会等名
      21st International Conference on Fusion Reactor Materials (ICFRM21)
    • 関連する報告書
      2023 実施状況報告書
    • 国際学会
  • [学会発表] Effects of Oxides on the Microstructure and Properties of ODS-CLAM Steel2023

    • 著者名/発表者名
      Gaofan Zhu, Qunying Huang, Yunfei Bai, Jingjie Shen
    • 学会等名
      21st International Conference on Fusion Reactor Materials (ICFRM21)
    • 関連する報告書
      2023 実施状況報告書
    • 国際学会

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公開日: 2023-04-13   更新日: 2024-12-25  

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