研究者詳細

顔写真

コウ　デンテイ
耿　殿程
Diancheng Geng
所属
金属材料研究所　材料設計研究部　原子力材料工学研究部門
職名
助教
学位

  • 博士（工学）（東北大学）

  • 修士（工学）（東北大学）

e-Rad 研究者番号
41026819

経歴 2

  • 2026年4月 ～ 継続中
    東北大学金属材料研究所　助教

  • 2024年10月 ～ 2026年3月
    東北大学金属材料研究所　日本学術振興会特別研究員PD

学歴 3

  • 北京科技大学　材料学院　材料物理専攻

    2015年9月 ～ 2049年6月

  • 東北大学　大学院工学研究科　量子エネルギー工学専攻

    2021年10月 ～ 2024年9月

  • 東北大学　大学院工学研究科　量子エネルギー工学専攻

    2019年10月 ～ 2021年9月

研究分野 1

  • ナノテク・材料 / 構造材料、機能材料 / 極限環境構造材料、環境耐性、超微小試験技術

論文 20

  1. Anomalous dose dependence of neutron irradiation hardening and phase separation in Fe–Cr alloys

    Kaito Kamiyama, Diancheng Geng, Koji Inoue, Takeshi Toyama, Kiyohiro Yabuuchi, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    Materials Science and Engineering: A　2026年8月

    DOI： 10.1016/j.msea.2026.150434 　

  2. Effect of Ta addition of W on recovery behavior of hardening by neutron irradiated at 290 oC under very low neutron damage level

    Minha Park, Diancheng Geng, Kaito Mizuno, Shuhei Nogami, Akira Hasegawa, Ryuta Kasada

    Journal of Nuclear Materials　2026年7月

    DOI： 10.1016/j.jnucmat.2026.156663 　

  3. Kinetic threshold for α′ suppression in ion-irradiated Fe–Cr–Al alloys revealed by high-throughput mapping

    Y. Abe, A. Kubo, D. Geng, S. Yamashita, N. Okubo, T. Tsuru, T.T. Sasaki, H. Yu, R. Kasada, S. Ukai

    Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms　2026年7月

    DOI： 10.1016/j.nimb.2026.166135 　

  4. Mechanochemical reaction pathway of WO3 in high-energy ball milling of oxide dispersion strengthened Cu powders

    Zimo Gao, Hao Yu, Diancheng Geng, Feifan He, Minha Park, Yasuyuki Ogino, Akira Hasegawa, Sosuke Kondo, Ryuta Kasada

    Materialia　2026年5月

    DOI： 10.1016/j.mtla.2026.102738 　

  5. Effect of WO3 addition on the fabrication of oxide dispersion-strengthened Cu alloys by mechanical alloying of CuYZr alloy powders

    Zimo Gao, Hao Yu, Diancheng Geng, Koji Inoue, Yasuyuki Ogino, Sosuke Kondo, Ryuta Kasada

    Nuclear Materials and Energy　2026年3月

    DOI： 10.1016/j.nme.2026.102060 　

    ISSN：2352-1791

  6. Interfacial microstructure and adhesion evaluation of pre-oxidized alumina scales on FeCrAl ODS alloy under ion irradiation

    Hao Yu, Diancheng Geng, Minha Park, Yasuyuki Ogino, Naoko Oono-Hori, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Shigeharu Ukai

    Journal of Nuclear Materials　2026年3月

    DOI： 10.1016/j.jnucmat.2026.156464 　

    ISSN：0022-3115

  7. Enhanced oxidation resistance of high-manganese austenitic steels through mechanical alloying and oxide-dispersion strengthening

    Diancheng Geng, Hao Yu, Yasuyuki Ogino, Sosuke Kondo, Junichi Miyazawa, Ryuta Kasada

    Materials & Design　2025年12月

    DOI： 10.1016/j.matdes.2025.115218 　

  8. Effect of irradiation temperature on the microstructure and hardness of W-0.3Cr alloy after irradiation with 6.4 MeV Fe ions

    Jing Wang, Jingxian Sun, Yingying Jia, Yifan Zhang, Yuji Hatano, Diancheng Geng, Katsuya Suzuki, Chang Chen, Laima Luo, Kiyohiro Yabuuchi, Ryuta Kasada

    Materials & Design　2025年11月

    DOI： 10.1016/j.matdes.2025.114783 　

  9. Ion-mixing-induced mitigation of swelling and modulus reduction in irradiated SiC fibers

    Xinwei Yuan, Sosuke Kondo, Diancheng Geng, Kiyohiro Yabuuchi, Hao Yu, Yasuyuki Ogino, Ryuta Kasada

    Journal of the European Ceramic Society　2025年11月

    DOI： 10.1016/j.jeurceramsoc.2025.117563 　

  10. Fracture behavior and grain boundary cohesion of alumina scales formed on ion-irradiated FeCrAl-ODS alloy

    Hao Yu, Diancheng Geng, Yasuyuki Ogino, Naoko Oono-Hori, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Shigeharu Ukai

    Journal of Nuclear Materials　2025年2月

    DOI： 10.1016/j.jnucmat.2025.155663 　

  11. Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests

    Diancheng Geng, Hao Yu, Masami Ando, Hiroyasu Tanigawa, Hironori Kurotaki, Takashi Nozawa, Sosuke Kondo, Ryuta Kasada

    Journal of Nuclear Materials　2024年5月

    DOI： 10.1016/j.jnucmat.2024.155013 　

    ISSN：0022-3115

  12. Effects of Cr and Si Addition on the High-Temperature Oxidation Resistance in High-Mn Alumina-forming Oxide Dispersion Strengthened Austenitic Steels

    Diancheng Geng, Hao Yu, Xinwei Yuan, Sosuke Kondo, Junichi Miyazawa, Ryuta Kasada

    Nuclear Materials and Energy　2023年12月21日

    DOI： 10.1016/j.nme.2023.101572 　

    ISSN：2352-1791

  13. Practical method to determine the effective zero-point of indentation depth for continuous stiffness measurement nanoindentation test with Berkovich tip

    Diancheng Geng, Hao Yu, Yasuki Okuno, Sosuke Kondo, Ryuta Kasada

    Scientific Reports　12　(1)　2022年12月

    出版者・発行元： Springer Science and Business Media {LLC}

    DOI： 10.1038/s41598-022-10490-8 　

    ISSN：2045-2322

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    <jats:title>Abstract</jats:title><jats:p>The zero-point of indentation depth in nanoindentation or depth-sensing instrumented indentation tests should be precisely set to evaluate the indentation hardness and indentation elastic modulus of materials to be tested, especially at shallow depths. A critical contact stiffness value has been widely used to determine the zero-point in nanoindentation tests with a Berkovich tip using the continuous stiffness measurement (CSM) method. However, this criterion occasionally gives an inadequate zero-point owing to the surface roughness of materials, the vibration of the testing system, and the flaws of the CSM method at shallow depth. This study proposes a practical method to determine the effective zero-point of indentation depth, which was obtained linearly at the zero-point of contact stiffness and extrapolated from the depth-dependent contact stiffness values, except for those at initially unstable contact depths. The proposed method enables nanoindentation tests to obtain a constant indentation elastic modulus and low deviation of nanoindentation hardness of homogenously fused silica and metallic materials, which provides an efficient way to obtain more accurate test data.</jats:p>

  14. Toward the correlation of indentation hardness in micro- and nano-scale: understanding of indentation edge behaviors in Fe–Cr alloys

    Diancheng Geng, Hao Yu, Sosuke Kondo, Ryuta Kasada

    Journal of Materials Science　57　(28)　13736-13755　2022年7月

    出版者・発行元： Springer Science and Business Media {LLC}

    DOI： 10.1007/s10853-022-07461-9 　

    ISSN：0022-2461 1573-4803

  15. Evaluating the irradiation hardening of reactor pressure vessel steels by nanoindentation hardness test and micropillar compression test

    Yuyang Zheng, Diancheng Geng, Hao Yu, Sosuke Kondo, Akihiko Kimura, Hideki Yuya, Ryuta Kasada

    Journal of Nuclear Science and Technology　1-12　2022年5月9日

    出版者・発行元： Informa {UK} Limited

    DOI： 10.1080/00223131.2022.2067258 　

    ISSN：0022-3131 1881-1248

  16. Effects of zirconium addition on the material properties and microstructure of ODS-Cu alloys

    Zimo Gao, Hao Yu, Diancheng Geng, Yuchen Liu, Sosuke Kondo, Yasuki Okuno, Ryuta Kasada

    Journal of Alloys and Compounds　899　163328-163328　2022年4月

    出版者・発行元： Elsevier {BV}

    DOI： 10.1016/j.jallcom.2021.163328 　

    ISSN：0925-8388

  17. Heavy-ion irradiation and post-irradiation annealing effects in explosion-welded CuCrZr/316LN joints for ITER application

    Xiaoou Yi, Yufeng Du, Diancheng Geng, Zihao Li, Wentuo Han, Pingping Liu, Jiming Chen, Kiyohiro Yabuuchi, Kenta Yoshida, Somei Ohnuki, Qian Zhan, Farong Wan, Yasuyoshi Nagai

    Materials Characterization　178　111252-111252　2021年8月

    出版者・発行元： Elsevier {BV}

    DOI： 10.1016/j.matchar.2021.111252 　

    ISSN：1044-5803

  18. Defect characterization, mechanical and thermal property evaluation in CVD-W after low-dose neutron irradiation

    Xiaoou Yi, Lei Zhang, Wentuo Han, Jiao Chen, Pingping Liu, Yanwei Lv, Jiupeng Song, Luwei Xue, Diancheng Geng, Kenta Yoshida, Takeshi Toyama, Qian Zhan, Farong Wan, Somei Ohnuki, Yasuyoshi Nagai

    International Journal of Refractory Metals and Hard Materials　85　105004-105004　2019年12月

    出版者・発行元： Elsevier {BV}

    DOI： 10.1016/j.ijrmhm.2019.105004 　

    ISSN：0263-4368

  19. Application of Small Specimen Test Technique to Evaluate Creep Behavior of Austenitic Stainless Steel

    Bintao Yu, Wentuo Han, Zhenfeng Tong, Diancheng Geng, Chenlong Wang, Yingchao Zhao, Wen Yang

    Materials　12　(16)　2541-2541　2019年8月9日

    出版者・発行元： {MDPI} {AG}

    DOI： 10.3390/ma12162541 　

    ISSN：1996-1944

    詳細を見る 詳細を閉じる

    <jats:p>Small specimen test techniques (SSTT) are highly demanded in the nuclear field. In the present work, SSTT was applied to the creep tests of 15-15Ti austenitic steel. The creep behaviors of specimens with miniaturized and standard sizes were contrastively studied. The feasibility of SSTT is verified after tests under more than 20 creep conditions. The results that were obtained by miniaturized specimens are relatively conservative and they can be securely applied. The stress exponent and apparent activation creep energy of 15-15Ti are calculated as 7.7 and 428 kJ/mol, respectively. The creep microstructures are characterized by the evolution of dislocations, deformation twins, and precipitates.</jats:p>

  20. Characterization of interface irradiation damage in Ti-clad V-4Cr-4Ti composite material

    Ran-Ran Li, Yi-Fan Zhang, Dian-Cheng Geng, Gao-Wei Zhang, Hideo Watanabe, Wen-Tuo Han, Fa-Rong Wan an, n

    Acta Physica Sinica　68　(21)　216101-216101　2019年

    出版者・発行元： Acta Physica Sinica, Chinese Physical Society and Institute of Physics, Chinese Academy of Sciences

    DOI： 10.7498/aps.68.20191204 　

    ISSN：1000-3290

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    <jats:p xml:lang="en">The development of electrically insulating coatings is extremely important for the lithium/vanadium (Li/V) blanket of the fusion reactor. However, Li/V cladding materials suffer many problems such as tritiumpermeation and material corrosion. Thus, it is very important to find suitable insulating, tritium-resistant and corrosion-resistant coatings. So, the " V-alloy/Ti/AlN” bilayer coating was proposed by our group in previous study for the first time. In this paper, the evolution of the hardness, irradiation defects and microstructure of the Ti-clad V-4Cr-4Ti composite material after Fe&lt;sup&gt;10+&lt;/sup&gt; implantation are studied by transmission electron microscopy (TEM) and nanoindentation. According to the characteristics of the composition and microstructure, V-4Cr-4Ti/Ti composite material can be divided into four zones: V-4Cr-4Ti matrix, interface I (the interface near V-4Cr-4Ti matrix), interface II (the interface near Ti matrix), and Ti matrix. The nanoindentation results show that radiation hardening occurs in all regions during irradiation. The radiation hardening in the interface is lower than in the V-4Cr-4Ti and Ti matrix. Thus, the interface of heterogeneous material exhibits fine resistance to radiation hardening. The experimental values of hardness are much higher than the values calculated by the dispersed barrier hardening model. One reason for the discrepancy is that the theoretical values are calculated under the hypothesis of the uniform loop distribution. Actually, a large number of dislocation loops accumulate and tangle with each other in the samples. In addition, the formation of the precipitates is also one of the key factors. The TEM results show that the irradiation defects in the interface are low in density, large in size, and uniform in distribution. As a contrast, high density, small size and twisted dislocation loops are observed in irradiated V-4Cr-4Ti and Ti matrix. These results indicate that the interface can play a critical role in the resistance to irradiation damage. Few tiny Ti-rich precipitates appear in the V-4Cr-4Ti matrix, while there are large quantities of Ti precipitates in the interface after irradiation. Moreover, the number and size of precipitates in the interface I are larger than those in the interface II due to the formation of a few V-rich precipitates in the interface I. The formation of precipitations changes the proportion of V/Ti, which leads to the transformation from &lt;i&gt;β&lt;/i&gt;-Ti to &lt;i&gt;α&lt;/i&gt;-Ti in the interface.</jats:p>

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共同研究・競争的資金等の研究課題 1

  1. 耐酸化性と強度延性の向上を可能とする低放射化酸化物分散強化オーステナイト鋼の開発

    GENG DIANCHENG

    提供機関：Japan Society for the Promotion of Science

    制度名：Grants-in-Aid for Scientific Research

    研究種目：Grant-in-Aid for JSPS Fellows

    研究機関：Tohoku University

    2024年4月23日 ～ 2026年3月31日

    詳細を見る 詳細を閉じる

    本研究では、非磁性を有し、かつ高強度・高延性・高温酸化耐性を兼ね備えた次世代核融合炉構造材料として期待される高Mnオーステナイト系酸化物分散強化（ODS）鋼の開発を目指し、Fe-30Mn-5Al-1Si（質量％）をベースとした合金を対象に、材料設計および各種基礎特性の評価を進めてきた。 まず、高温酸化耐性に関して、機械的合金化（Mechanical Alloying, MA）および放電プラズマ焼結（SPS）を用いてY2O3を分散させたODS鋼を作製し、500℃の高温環境下での酸化挙動を評価した。その結果、酸化物粒子の添加およびMA処理によって粒界・粒内に多くの界面が導入され、酸化スケール形成挙動に大きな影響を与えることが明らかとなった。特に、アモルファス状の酸化アルミナは、Siの添加によりアルミノシリケートを含む複合酸化物層へと変化し、これが酸化膜の緻密性を高め、長時間使用時における酸化耐性の大幅な向上に寄与することが示された。 次に、室温および500℃における引張試験を実施し、力学特性の評価を行った。高温域では、従来のODSフェライト鋼と同等の引張強度を示しながら、室温ではそれを凌駕する優れた強度－延性バランスを有することが確認された。この高靭性は、酸化物粒子が変形双晶の発生を促進し、加工硬化を高めることに起因すると考えられる。特に、EBSD解析によって、ナノ粒組織内部においても明確な双晶や変形帯が形成されていることが確認され、ナノ構造領域が塑性変形に積極的に関与していることが示唆された。 これらの結果より、開発中の高Mn ODS鋼は、核融合炉応用に求められる特性を高いレベルで満たす可能性を持つことが示され、今後の照射試験やさらなる高温特性評価への展開が期待される。