Updated on 2024/10/01

Information

 

写真a

 
SUMITA TAKEHIRO
 
Organization
Faculty of Engineering Department of Materials Science and Engineering Assistant Professor
School of Engineering (Concurrent)
Title
Assistant Professor

Research Areas

  • Nanotechnology/Materials / Metallic material properties

  • Humanities & Social Sciences / Linguistics

  • Nanotechnology/Materials / Inorganic materials and properties

  • Humanities & Social Sciences / Educational technology

  • Energy Engineering / Nuclear engineering

Degree

  • PhD. in Engineering (Mar, 2019, Tokyo Institute of Technology)

Research History

  • Kyushu University Department of Materials Assistant Professor

    2023.4 - Present

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  • Japan Atomic Energy Agency (National Research and Development Agency) CLADS Researcher

    2019.4 - 2023.3

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  • 国立研究開発法人日本原子力研究開発機構

    国立研究開発法人日本原子力研究開発機構

Research Interests・Research Keywords

  • Research theme:metallurgy

    Keyword:metallurgy

    Research period: 2024

  • Research theme:fuel debris

    Keyword:fuel debris

    Research period: 2024

  • Research theme:boron analysis

    Keyword:boron analysis

    Research period: 2024

  • Research theme:Seminar

    Keyword:Seminar

    Research period: 2024

  • Research theme:Skopos theory

    Keyword:Skopos theory

    Research period: 2024

  • Research theme:Prompt gamma-ray analysis for accurate boron determination

    Keyword:boron quantitative analysis

    Research period: 2023.4

Awards

  • 若手ポスター発表賞

    2023.9   一般社団法人資源・素材学会  

  • 若手ポスター発表賞

    2023.9   一般社団法人資源・素材学会  

    墨田 岳大, 大澤 崇人, 池田 篤史, 齊藤 敬高, 中島 邦彦

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  • 令和元年度関東工学教育協会賞(論文・論説賞)

    2020.5   関東工学教育協会  

  • 材料部会若手優秀賞,

    2019.9   日本原子力学会 材料部会  

  • 工学教育賞(論文・論説部門),

    2019.9   日本工学教育協会  

  • 最優秀賞,

    2018.8   IRIDシンポジウム2018 燃料デブリ取り出しに挑む-Ⅱ

  • 最優秀フロンティアスピリット賞,

    2018.3   次世代イニシアチブ廃炉技術カンファレンス(NDEC-3)

  • 研究奨励賞,

    2018.3   次世代イニシアチブ廃炉技術カンファレンス(NDEC-3)

  • Best Presentation Award,

    2017.12   ACEEES   Best Presentation Award,

  • 最優秀フロンティアスピリット賞,

    2017.3   次世代イニシアチブ廃炉技術カンファレンス(NDEC-2)

  • 研究奨励賞,

    2017.3   次世代イニシアチブ廃炉技術カンファレンス(NDEC-2)

  • Best Presentation Award,

    2015.12   ACEEES   Best Presentation Award,

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Papers

  • Evaluation of Analytical Uncertainty in Quantitative Determination of Elements - The Case of Boron Reviewed

    Takehiro Sumita, Takahito Osawa, I-Huan Chiu, Atsushi Ikeda-Ohno

    Analytica Chimica Acta   15 ( 1329 )   343256 - 343256   2024.9   ISSN:0003-2670

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    Authorship:Lead author, Corresponding author   Language:English   Publishing type:Research paper (scientific journal)   Publisher:Elsevier BV  

    DOI: 10.1016/j.aca.2024.343256

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  • Comparison of the viscoelastic properties and viscosity of suspensions determined by oscillation and creep testing

    Nakanishi Kento, Sumita Takehiro, Saito Noritaka, Nakashima Kunihiko

    ISIJ International   advpub ( 0 )   2024   ISSN:09151559 eISSN:13475460

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:The Iron and Steel Institute of Japan  

    <p>Knowledge of the viscoelastic properties of suspensions is essential for many industrial processes. Although oscillation and creep testing are widely used to measure the viscoelastic properties of complex fluids, few studies on the correlation between the viscoelastic properties measured using these methods have been published. This study aims to provide insights into the differences between these methods and determine which method is better suited for a particular application. The room-temperature viscoelastic properties of a suspension composed of polyethylene beads dispersed in a silicone oil matrix were measured by oscillation and creep testing and compared. The results of oscillation testing indicated that the suspension showed weakly elastic deformation, whereas the results of creep testing revealed that the suspension was relatively elastic, with the liquid phase showing lower viscosity. In addition, the viscosity measured by oscillation testing was lower than that measured by creep testing. When the imposed flow causes microstructural changes, such as when the shear flow and particle‒particle contact induce aggregation, the analyzed flow property considerably differs between testing methods.</p>

    DOI: 10.2355/isijinternational.isijint-2024-078

    CiNii Research

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  • Potential bacterial alteration of nuclear fuel debris: a preliminary study using simulants in powder and pellet forms Reviewed

    Jiang Liu, Yuma Dotsuta, Takehiro Sumita, Toru Kitagaki, Toshihiko Ohnuki, Naofumi Kozai

    Journal of Radioanalytical and Nuclear Chemistry   331 ( 6 )   2785 - 2794   2022.5   ISSN:02365731

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    Potential bacterial alteration of nuclear fuel debris: a preliminary study using simulants in powder and pellet forms

    DOI: 10.1007/s10967-022-08324-y

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  • Direct in-situ temperature measurement for lamp-based heating device Reviewed

    Takehiro Sumita, Ayako Sudo, Masahide Takano, Atsushi Ikeda-Ohno

    Science and Technology of Advanced Materials: Methods   2 ( 1 )   50 - 54   2022.1   eISSN:2766-0400

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Informa UK Limited  

    Direct in-situ temperature measurement for lamp-based heating device

    DOI: 10.1080/27660400.2022.2035097

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  • High temperature reaction of multiple eutectic-component system: the case of solid metallic Zr and molten stainless steel-B4C Reviewed

    Takehiro Sumita, Masaaki Kobata, Masahide Takano, Atsushi Ikeda-Ohno

    Materialia   20   101197 - 101197   2021.8

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    Language:Others   Publishing type:Research paper (scientific journal)  

    DOI: 10.1016/j.mtla.2021.101197

  • Solidification and re-melting mechanisms of SUS-B4C eutectic mixture Reviewed

    Takehiro Sumita, Toru Kitagaki, Masahide Takano, Atsushi Ikeda-Ohno

    Journal of Nuclear Materials   543   152527 - 152527   2020.9

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    Language:English   Publishing type:Research paper (scientific journal)  

    Solidification and re-melting mechanisms of SUS-B4C eutectic mixture
    Fundamental understanding of the high-temperature interaction between stainless steel (SUS) and B4C is indispensable for estimating and characterizing the fuel debris generated during severe accidents of boiling water reactors (BWR), such as Fukushima Dai-ichi Nuclear Power Station (FDNPS, also referred to as "1F") in Japan. This study aims at systematically characterizing the solidified products of molten SUS-B4C mixtures by powder X-ray diffraction (PXRD), scanning electron microscopy-energy dispersive X-ray spectroscopy (SEM-EDS), and thermogravimetry-differential thermal analysis (TG-DTA) with a range of the B4C content relevant to the fuel debris composition expected at 1F, in order to elucidate the solidification and re-melting mechanisms. The results indicated that gamma-Fe and (Cr,Fe)(2)B are the major solidified phases when the B4C content is below 3 mass&#37;, while (Cr,Fe)(23)(C,B)(6) is formed as an additional third phase when the B4C content exceeds 3 mass&#37;. The solidification of molten SUS-B4C mixture and remelting of solidified SUS-B4C melt are eutectic, which is mainly controlled by the pseudo-binary Fe-B system that is influenced by the C and Cr content and additional minor components such as Mo. (C) 2020 Elsevier B.V. All rights reserved.

    DOI: 10.1016/j.jnucmat.2020.152527

  • Dissolution behavior of solid stainless steel by its molten eutectic mixture with B4C under dynamic condition Reviewed

    Takehiro Sumita, Yoshinao Kobayashi

    Progress in Nuclear Energy   117   2019.11

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    Language:English   Publishing type:Research paper (scientific journal)  

    Dissolution behavior of solid stainless steel by its molten eutectic mixture with B4C under dynamic condition

    DOI: 10.1016/j.pnucene.2019.103094

  • Investigation of corrosion-erosion behavior of stainless steel considering SS-B4C melt Reviewed

    Takehiro Sumita, Yoshinao Kobayashi

    Journal of nuclear materials   515   71 - 79   2019.3

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    Investigation of corrosion-erosion behavior of stainless steel considering SS-B4C melt

    DOI: 10.1016/j.jnucmat.2018.12.026

  • The release behavior of boron and silicon from degraded absorber rods on core degradation during BWR severe accident Reviewed

    Ayumi Itoh, Takehiro Sumita, Masanori Kajihara, yoshinao kobayashi

    Journal of nuclear materials   514   101 - 108   2019.2

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    The release behavior of boron and silicon from degraded absorber rods on core degradation during BWR severe accident

    DOI: 10.1016/j.jnucmat.2018.11.001

  • Quantitative Analysis Method for Determination of Boron Concentration in Stainless Steel-B₄C Alloy by ICP-OES Reviewed

    18 ( 4 )   247 - 249   2018.12

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  • 理工系教育におけるゼミ形成因子とエフェクトの研究‐スコポス理論を利用した試み Reviewed

    墨田岳大, 野原佳代子

    工学教育   66 ( 3 )   3_2‐3_9(J‐STAGE) - 3_9   2018.5

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    Language:Japanese   Publishing type:Research paper (scientific journal)  

    In this research, an analysis of seminars diversity and their characteristics based on translation studies (Skopos theory) was conducted to obtain knowledge to improve the quality of seminars in university laboratory. From the investigation that regarded expression of the seminars as intersemiotic translation, seven types of activities were found : (1) introducing papers, (2) reading materials in turn, (3) progress report, (4) presentation, (5) discussion, (6) lecture, and (7) others. With the focus on progress report, the relevance between the seminar formation factors and students&amp;rsquo; growth was considered by integrating the factors with Skopos. With the idea that the diversity was created by the factors, it was inductively concluded that by adjusting factors, enhancement of specific educational effects can be achieved.

    DOI: 10.4307/jsee.66.3_2

  • Dissolution behavior of core structure materials by molten corium in boiling water reactor plants during severe accidents Reviewed

    Takehiro Sumita, Kentaro Urata, Yuya Morita, Yoshinao Kobayashi

    Journal of Nuclear Science and Technology   55 ( 3 )   267 - 275   2018.3

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    Dissolution behavior of core structure materials by molten corium in boiling water reactor plants during severe accidents
    For the decommissioning of the Fukushima Daiichi Nuclear Power Plant, it is necessary to consider the access route to the fuel debris for its removal, which can be determined by knowing the corruption situation of the core support structure. To predict the damage condition of reactor vessel, dissolution behavior of the core structure material should be understood. In this study, the dissolution behavior of core structure materials (stainless steel) by molten metallic corium (stainless steel + B4C) originated from control rod and its cladding was investigated. As a result of immersion experiment, it was found that there were two types of dissolution mode in this system: (1) chemical dissolution by eutectic reaction between Fe and B and (2) physical dissolution caused by the grains falling off from solid steel due to infiltration of molten metal. Moreover, on the basis of kinetic analysis, it was considered that the chemical dissolution in this system was slow. Therefore, the dissolution is considered to mainly occur through the mechanism that physical dissolution precedes chemical dissolution.

    DOI: 10.1080/00223131.2017.1394234

  • Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C alloy Reviewed

    Jiang Liu, Yuya Morita, Kentaro Urata, Takehiro Sumita, Yoshinao Kobayashi

    Energy Procedia   131   371 - 378   2017.12

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    Language:English   Publishing type:Research paper (other academic)  

    DOI: 10.1016/j.egypro.2017.09.469

  • In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation Reviewed

    Takehiro Sumita, Mitsutoshi Ueda, Masao Takeyama

    Proceedings of The 1st International Conference on Advanced High-Temperature Materials Technology for Sustainable and Reliable Power Engineering(123HiMAT-2015)   173 - 176   2016.3

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    In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation

  • 沸騰水型軽水炉過酷事故時の制御棒由来メタル系コリウムによるステンレス鋼の破損に関する研究(学位論文)

    墨田岳大

    東京工業大学   1900

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    Language:Japanese  

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Presentations

  • 即発γ線分析を利用したホウ素濃度の精密決定

    墨田岳大, 大澤崇人, 池田篤史

    第14回 日本ホウ素・ホウ化物研究会  2022.2 

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  • Dissolution behavior of solid stainless steel by its molten eutectic mixture with B4C: experimental investigation International conference

    Material Science for Severe Accident and Fukushima-Daiichi Decommissioning Workshop 2019 (FRC2019)  2019.7 

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    Dissolution behavior of solid stainless steel by its molten eutectic mixture with B4C: experimental investigation

  • 燃料模擬物質CeO2-xにおける空気雰囲気中のO/M比変化挙動に関する研究

    服部 亮平, 佐藤 勇, 墨田 岳大, 小林 能直

    日本原子力学会2019年春の年会  2019.3 

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  • Corrosion-erosion of solid stainless steel by molten metallic corium: experimental investigation International conference

    2018.7 

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    Corrosion-erosion of solid stainless steel by molten metallic corium: experimental investigation

  • メタル系溶融コリウムによる炉心構造物破損形態の解明

    次世代イニシアチブ廃炉技術カンファレンス(NDEC-3)  2018.3 

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  • 低酸素分圧下でのCaO-SiO2-Cr2O3スラグ中のCrOxの溶解度測定

    加藤千聖, 墨田岳大, 浦田健太郎, 小林能直

    日本鉄鋼協会第175回春季講演大会  2018.3 

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  • 動的条件下におけるSS固相のSS-B4C共晶溶融物による破損現象

    墨田岳大, 小林能直

    日本原子力学会2018年春の年会  2018.3 

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  • 沸騰水型軽水炉過酷事故における炉心溶融物の挙動(1)メタル系,酸化物系溶融物によるステンレス鋼製構造物の破壊

    墨田岳大, 小林能直, 植田滋, 中桐俊男

    日本原子力学会秋の大会予稿集(CD-ROM)  2018.8 

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  • 流れのあるメタル系溶融デブリ中でのステンレス構造物破損速度の検討

    墨田岳大, 小林能直

    IRID シンポジウム2018 燃料デブリ取り出しに挑む-Ⅱ  2018.8 

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  • Collapse Behavior of Reactor Core Materials in BWR During Severe Accidents International conference

    MIT-Tokyo Tech Workshop on Innovative Nuclear Energy System (MT-INES)  2017.10 

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    Collapse Behavior of Reactor Core Materials in BWR During Severe Accidents

  • Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

    LIU Jiang, SUMITA Takehiro, KOBAYASHI Yoshinao

    2017.8 

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    Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

  • Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

    LIU Jiang, SUMITA Takehiro, KOBAYASHI Yoshinao

    2017.8 

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    Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

  • Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy International conference

    CLADS wokshop  2017.7 

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    Dissolution behavior of stainless steel into Fe-Cr-Ni-B-C alloy

  • Investigation on the Dissolution Behavior of Core Structure Materials by Molten Corium in Boiling Water Reactor Plants during Severe Accidents International conference

    The Sixth International Education Forum on Environment and Energy Science  2017.12 

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    Investigation on the Dissolution Behavior of Core Structure Materials by Molten Corium in Boiling Water Reactor Plants during Severe Accidents

  • Investigation on the Fracture Behavior of Core Structure Materials by Molten Corium in Boiling Water Reactor Plants during Severe Accidents International conference

    CLADS Workshop  2017.10 

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    Investigation on the Fracture Behavior of Core Structure Materials by Molten Corium in Boiling Water Reactor Plants during Severe Accidents

  • Investigation on the Fracture Behavior of Core Structure materials by Molten Corium in Boiling Water Reactor Plants during severe accidents International conference

    TITECH-CRIEPI-JAEA Joint Workshop  2017.7 

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    Investigation on the Fracture Behavior of Core Structure materials by Molten Corium in Boiling Water Reactor Plants during severe accidents

  • 沸騰水型軽水炉過酷事故時の炉心構造物の破損形態の解明―溶融Fe‐Cr‐Ni‐B‐Cによるステンレス鋼の破損モードの検討―

    墨田岳大, 小林能直, 植田滋, 中桐俊男

    日本原子力学会秋の大会予稿集(CD-ROM)  2017.8 

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  • 沸騰水型軽水炉過酷事故時の炉心構造物破損形態の解明

    墨田岳大, 小林能直

    IRIDシンポジウム2017 inいわき  2017.8 

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  • 沸騰水型軽水炉過酷事故時の炉心構造物破損形態の解明

    墨田 岳大, 守田 祐哉, 浦田 健太郎, 小林 能直

    次世代イニシアチブ廃炉技術カンファレンス(NDEC-2)  2017.3 

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  • 高温・高圧水蒸気環境下における原子炉構造材へのCs吸着挙動評価

    墨田岳大, 米川夏津夫, 関尾佳弘, 佐藤勇, 小林能直, 逢坂正彦, 前田宏治, 赤坂尚昭

    日本原子力学会春の年会予稿集(CD-ROM)  2017.3 

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  • Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C melts International conference

    The Fifth International Symposium on Innovative Nuclear Energy Systems (INES-5)  2016.10 

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    Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C melts

  • In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation International conference

    The 1st International Conference on Advanced High-Temperature Materials Technology for Sustainable and Reliable Power Engineering(123HiMAT-2015)  2016.3 

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    In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation

  • Investigation on the Erosion Behavior of Molten Core in Nuclear Power Plants During Severe Accidents International conference

    The Fifth International Education Forum on Environment and Energy Science  2016.12 

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    Investigation on the Erosion Behavior of Molten Core in Nuclear Power Plants During Severe Accidents

  • SUS304ステンレス鋼の溶融Fe‐Cr‐Ni‐B‐C合金中への溶解挙動

    小林能直, 守田祐哉, 墨田岳大, 植田滋, 中桐俊男

    日本原子力学会秋の大会予稿集(CD-ROM)  2016.8 

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  • In-situ Observation of the Cracking Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation International conference

    The Fourth International Education Forum on Environment and Energy Science  2015.12 

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    In-situ Observation of the Cracking Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation

  • Fe‐20Cr‐35Ni‐2.5Nb(at.&#37;)鋼に形成する酸化皮膜の性状と室温引張変形における破壊挙動

    墨田岳大, 上田光敏, 高田尚記, 竹山雅夫

    日本金属学会講演概要(CD-ROM)  2014.9 

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  • 沸騰水型軽水炉過酷事故時の炉心構造物破損形態の解明

    墨田岳大, 小林能直

    IRIDシンポジウム2017 inいわき  2017.8 

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  • 沸騰水型軽水炉過酷事故時の炉心構造物破損形態の解明

    墨田 岳大, 守田 祐哉, 浦田 健太郎, 小林 能直

    次世代イニシアチブ廃炉技術カンファレンス(NDEC-2)  2017.3 

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  • 高温・高圧水蒸気環境下における原子炉構造材へのCs吸着挙動評価

    墨田岳大, 米川夏津夫, 関尾佳弘, 佐藤勇, 小林能直, 逢坂正彦, 前田宏治, 赤坂尚昭

    日本原子力学会春の年会予稿集(CD-ROM)  2017.3 

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  • Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C melts International conference

    The Fifth International Symposium on Innovative Nuclear Energy Systems (INES-5)  2016.10 

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    Language:English  

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    Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C melts

  • In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation International conference

    The 1st International Conference on Advanced High-Temperature Materials Technology for Sustainable and Reliable Power Engineering(123HiMAT-2015)  2016.3 

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    Language:English  

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    In-Situ Observation of the Fracture Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation

  • Investigation on the Erosion Behavior of Molten Core in Nuclear Power Plants During Severe Accidents International conference

    The Fifth International Education Forum on Environment and Energy Science  2016.12 

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    Investigation on the Erosion Behavior of Molten Core in Nuclear Power Plants During Severe Accidents

  • SUS304ステンレス鋼の溶融Fe‐Cr‐Ni‐B‐C合金中への溶解挙動

    小林能直, 守田祐哉, 墨田岳大, 植田滋, 中桐俊男

    日本原子力学会秋の大会予稿集(CD-ROM)  2016.8 

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  • In-situ Observation of the Cracking Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation International conference

    The Fourth International Education Forum on Environment and Energy Science  2015.12 

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    In-situ Observation of the Cracking Behavior of the Oxide Scale on the Fe-20Cr-35Ni-2.5Nb-0.03B-0.1Zr Steel during Tensile Deformation

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    墨田岳大, 上田光敏, 高田尚記, 竹山雅夫

    日本金属学会講演概要(CD-ROM)  2014.9 

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  • Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C alloy

    Jiang LIU, Yuya MORITA, Kentaro URATA, Takehiro SUMITA, Yoshinao KOBAYASHI

    2016.11 

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    Dissolution behavior of SUS304 stainless steel into Fe-Cr-Ni-B-C alloy

  • Dissolution behavior of SUS304 stainless steel into molten Fe-Cr-Ni-B-C alloy

    2016.9 

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    Dissolution behavior of SUS304 stainless steel into molten Fe-Cr-Ni-B-C alloy

  • Fe2O3-Cs2O系融体の粘度に及ぼすCs2O/Fe2O3比の影響

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • Oscillatory concentric cylinder法による高固相率サスペンションの粘弾性評価

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    一般社団法人資源・素材学会 九州支部 2023年度総会・春季例会・若手研究者および技術者の研究発表会  2023.5 

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  • サスペンションの粘性挙動に及ぼす外部電場の影響

    畠山大知, 墨田岳大, 齊藤敬高, 中島邦彦

    日本実験力学会 2023 年度年次講演会  2023.8 

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  • サスペンションのみかけ粘度に及ぼす固液界面電荷の影響

    畠山 大知, 墨田 岳大, 齊藤 敬高, 中島 邦彦

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  • 交流インピーダンス法を用いた模擬フォーミングスラグの生成挙動に及ぼす固相の影響評価

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    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 室温サスペンションの見かけ粘性に及ぼす外部電場の影響

    畠山大知, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 軽元素ホウ素の精緻な分析

    墨田 岳大, 大澤 崇人, 池田 篤史, 齊藤 敬高, 中島 邦彦

    2023年度資源・素材関係学協会合同秋季大会  2023.9 

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  • 酸化セシウムを含む溶融酸化鉄の粘性評価

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    日本実験力学会 2023 年度年次講演会  2023.8 

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  • 酸化鉄を含む溶融セシウム酸化物の粘性評価

    中西 賢斗, 墨田 岳大, 齊藤 敬高, 中島 邦彦

    一般社団法人資源・素材学会 九州支部 2023年度総会・春季例会・若手研究者および技術者の研究発表会  2023.5 

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  • 高レベル放射性廃棄物処理用ガラス融体の高温物性調査および評価

    Jaehoon Park, 墨田岳大, 齊藤敬高, 中島邦彦, 相馬諒, 大和久耕平, 兼平憲男

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 高固相率サスペンションの粘弾性挙動に及ぼす第二液相の影響

    神拓玖実, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • ZrO2が分散した溶融SUS316L固液共存流体の粘度測定

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • ホウ素定量における分析確度評価

    墨田岳大, 大澤崇人, 池田篤史, 齊藤敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • 高固相率サスペンションの粘弾性特性評価

    齊藤敬高, 神拓玖実, 中西賢斗, 墨田岳大, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • 集光加熱下におけるその場温度測定

    墨田 岳大, 池田 篤史

    第44回日本熱物性シンポジウム  2023.11 

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  • 高固相率サスペンションの粘弾性特性評価

    齊藤敬高, 神拓玖実, 中西賢斗, 墨田岳大, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • 高固相率サスペンションの粘弾性挙動に及ぼす第二液相の影響

    神拓玖実, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 高レベル放射性廃棄物処理用ガラス融体の高温物性調査および評価

    Jaehoon Park, 墨田岳大, 齊藤敬高, 中島邦彦, 相馬諒, 大和久耕平, 兼平憲男

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 高レベル放射性廃棄物処理用ガラス融体の電気伝導率測定

    篠原しおん, PARK JAEHOON, 墨田岳大, 齊藤敬高, 中島邦彦, 大和久耕平, 畠山 克彦

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  • 高レベル放射性廃棄物処理用ガラス融体の粘度測定

    森本圭祐, Park Jaehoon, 墨田岳大, 齊藤敬高, 中島邦彦, 大和久耕平, 畠山克彦

    2024年度資源・素材学会九州支部 若手研究者および技術者の研究発表会  2024.5 

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  • 電気インピーダンストモグラフィ法による溶融スラグ中固相の観察

    小川 真人, 瀬川 颯, Yosephus Ardean Kurnianto Prayitno、Alief Avicenna Luthfie, 墨田 岳大, 中島 邦彦, 武居 昌宏, 齊藤 敬高

    令和6年度 材料プロセス談話会  2024.4 

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  • 電気インピーダンストモグラフィ法によるスラグ中固相の可視化

    小川真人, 墨田岳大, 齊藤敬高, 中島邦彦, 瀬川颯, Yosephus A K, Prayitno, Alief A Luthfie, 武居昌宏

    日本金属学会九州支部, 日本鉄鋼協会九州支部, 軽金属学会九州支部 2024年度 合同学術講演会  2024.6 

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  • 電気インピーダンストモグラフィ法による 固液共存スラグの可視化

    小川真人, 瀬川颯, Yosephus Ardean Kurnianto Prayitno、Alief Avicenna Luthfie, 墨田岳大, 中島邦彦, 武居昌宏, 齊藤敬高

    2024.3 

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  • In-situ temperature measurement for arc image furnace

    Takehiro Sumita, Atsushi Ikeda-Ohno

    The 44th Japan Symposium on Thermophysical Properties  2023.11 

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  • 酸化鉄を含む溶融セシウム酸化物の粘性評価

    中西 賢斗, 墨田 岳大, 齊藤 敬高, 中島 邦彦

    一般社団法人資源・素材学会 九州支部 2023年度総会・春季例会・若手研究者および技術者の研究発表会  2023.5 

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  • 酸化セシウムを含む溶融酸化鉄の粘性評価

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    日本実験力学会 2023 年度年次講演会  2023.8 

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  • Precise and accurate determination of boron in materials

    Takehiro Sumita, Takahito Owasa, Atsushi Ikeda-Ohno, Noritaka Saito, Kunihiko Nakashima

    2023.9 

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  • 放射性廃棄物の溶融処理に関わるCs2O-Fe2O3-SiO2系融体の粘度測定

    田中 智己, 中西 賢斗, 墨田 岳大, 齊藤 敬高, 中島 邦彦

    2024年度資源・素材関係学協会合同秋季大会  2024.9 

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  • 室温サスペンションの見かけ粘性に及ぼす外部電場の影響

    畠山大知, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • 固相が分散した高温酸化物融体の電気インピーダンストモグラフィ法による可視化

    小川 真人, 瀬川 颯, Yosephus Prayitno, Alief Luthfie, 墨田 岳大, 中島 邦彦, 武居 昌宏, 齊藤 敬高

    2024年度資源・素材関係学協会合同秋季大会  2024.9 

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  • 周期加熱冷却下におけるモールドフラックスの 結晶化挙動評価に向けた予備的検討

    木村麟太郎, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • 即発ガンマ線分析を応用したホウ素分析の高確度化

    池田 瑞, 墨田 岳大, 足立 達朗, 齊藤 敬高, 中島 邦彦, 大澤 崇人, 邱 奕寰, 池田 篤史

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • Precise determination of boron concentration by prompt γ-ray analysis

    Takehiro Sumita, Takahito Osawa, Atsushi Ikeda-Ohno

    2022.2 

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  • 交流インピーダンス法を用いた模擬フォーミングスラグの生成挙動に及ぼす固相の影響評価

    平野瑠花, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • ホウ素定量における分析確度評価

    墨田岳大, 大澤崇人, 池田篤史, 齊藤敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • ホウ素分析手法における定量不確かさ 〜評価手法の検討〜

    池田瑞, 墨田岳大, 足立達朗, 齊藤敬高, 中島邦彦, 大澤崇人, 邱奕寰, 池田篤史

    2024年度資源・素材学会九州支部 若手研究者および技術者の研究発表会  2024.5 

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  • サスペンションの粘性挙動に及ぼす外部電場の影響

    畠山大知, 墨田岳大, 齊藤敬高, 中島邦彦

    日本実験力学会 2023 年度年次講演会  2023.8 

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  • サスペンションのみかけ粘度に及ぼす固液界面電荷の影響

    畠山 大知, 墨田 岳大, 齊藤 敬高, 中島 邦彦

    一般社団法人資源・素材学会 九州支部 2023年度総会・春季例会・若手研究者および技術者の研究発表会  2023.5 

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  • キャピラリ破断⽅式による溶融モールドフラックスの流動特性評価

    中⻄賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    日本金属学会九州支部, 日本鉄鋼協会九州支部, 軽金属学会九州支部 2024年度 合同学術講演会  2024.6 

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  • ZrO2が分散した溶融SUS316L固液共存流体の粘度測定

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • Visualization of Molten Slag Suspension by Electrical Resistance Tomography

    Masato.Ogawa, S.Segawa, Y.A.K.Prayitno, A.A.Luthfie, T.Sumita, K.Nakashima, N.Saito, M.Takei

    MOLTEN2024  2024.6 

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  • Viscosity evaluation of ZrO2 dispersed molten stainless

    Kento Nakanishi, Takehiro Sumita, Noritaka Saito, Kunihiko Nakashima

    MOLTEN2024  2024.6 

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  • Oscillatory concentric cylinder法による高固相率サスペンションの粘弾性評価

    神 拓玖実, 墨田 岳大, 齊藤 敬高, 中島 邦彦

    一般社団法人資源・素材学会 九州支部 2023年度総会・春季例会・若手研究者および技術者の研究発表会  2023.5 

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  • JRR-3 における CdTe イメージング検出器を用いた BNCT-SPECT の開発

    邱奕寰, 大澤崇人, 墨田岳大, 池田瑞, 二宮和彦, 武田伸一郎, 南喬博, 高橋忠幸, 渡辺伸

    第20回中性子捕捉療法学会  2024.7 

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  • Fe2O3-Cs2O系融体の粘度に及ぼすCs2O/Fe2O3比の影響

    中西賢斗, 墨田岳大, 齊藤敬高, 中島邦彦

    ⽇本⾦属学会・⽇本鉄鋼協会・軽⾦属学会九州⽀部 令和5年度合同学術講演会  2023.6 

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  • EDS,WDSにおけるホウ素分析確度評価

    池田 瑞, 墨田 岳大, 足立 達朗, 齊藤 敬高, 中島 邦彦, 大澤 崇人, 邱 奕寰, 池田 篤史

    令和6年度 材料プロセス談話会  2024.4 

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  • CaSの高温濡れ性におよぼす溶鋼中Al,Sの影響

    小川真人, 墨田岳大, 齊藤敬高, 中島邦彦, 島村祐太, 吉岡孝宜

    鉄鋼協会第188回秋季講演大会  2024.9 

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  • CaSの⾼温濡れ性に及ぼす溶鋼組成の影響

    松野航太, 小川真人, 墨田岳大, 齊藤敬高, 中島邦彦, 島村祐太, 吉岡孝宜

    日本金属学会九州支部, 日本鉄鋼協会九州支部, 軽金属学会九州支部 2024年度 合同学術講演会  2024.6 

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  • CaO-SiO2-Al2O3-MgO系固液共存スラグの粘度に及ぼす外部電場の影響

    畠山大知, 墨田 岳大, 齊藤 敬高, 中島邦彦

    ⽇本鉄鋼協会 第187回春季公演大会  2024.3 

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  • ABSOLUTE EVALUATION OF ANALYTICAL UNCERTAINTY IN QUANTITATIVE DETERMINATION OF BORON

    Takehiro Sumita, Takahito Osawa, I-huan Chiu, Atsushi Ikeda-ohno, Noritaka Saito, Kunihiko Nakashima

    ISBB2024  2024.9 

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  • 広島湾沿岸で見つかった溶融粒子とは?

    佐藤 志彦, 遠藤 暁, 赤時 僚伽, 菖蒲 敬久, 冨永 亜希, 墨田 岳大

    日本放射化学会第68回討論会(2024)  2024.9 

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  • JRR-3におけるCdTe検出器を用いたBNCT-SPECTの開発

    邱 奕寰, 大澤 崇人, 墨田 岳大, 池田 瑞, 二宮 和彦, 武田 伸一郎, 南 喬博, 高橋 忠幸, 渡辺 伸

    日本放射化学会第68回討論会(2024)  2024.9 

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MISC

  • 金属材料の共晶溶融現象

    墨田岳大, 池田篤史

    Isotope News 10月号 (No.783)   2022.10

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  • 金属材料の共晶溶融現象 Invited

    Takehiro Sumita, Atsushi Ikeda-Ohno

    28 - 32   2022.10

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    Authorship:Lead author  

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  • 燃料デブリの正体を明らかにする -制御棒由来の金属系燃料デブリの形成メカニズム解明-

    墨田岳大

    原子力機構の研究開発成果 2021-22   2021.10

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  • 沸騰水型軽水炉過酷事故時の制御棒由来メタル系コリウムによる ステンレス鋼の破損に関する研究

    墨田岳大

    材料部会報 Nuclear Materials Letters   2019.12

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  • 第23回(2018年度)工学教育賞選考経過報告と受賞業績紹介 論文・論説部門:理工系教育におけるゼミ形成因子とエフェクトの研究―スコポス理論を利用した試み

    墨田岳大, 野原佳代子

    工学教育   2019.11

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  • Collapse Behavior of Core Structure Materials by Molten Metallic Corium in Boiling Water Reactor Plants during Severe Accidents

    Yoshinao Kobayashi, Takehiro Sumita

    Bulletin of the Laboratory for Advanced Nuclear Energy   2018.2

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    Collapse Behavior of Core Structure Materials by Molten Metallic Corium in Boiling Water Reactor Plants during Severe Accidents

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Professional Memberships

  • The Society of Boron, Borides and Related Materials of Japan

  • THE JAPAN SOCIETY FOR ANALYTICAL CHEMISTRY

  • ATOMIC ENERGY SOCIETY OF JAPAN

  • Japanese Society for Engineering Education

  • 日本鉄鋼協会

  • 関東工学教育協会

  • 関東工学教育協会

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  • 日本鉄鋼協会

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  • Japanese Society for Engineering Education

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  • ATOMIC ENERGY SOCIETY OF JAPAN

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  • THE JAPAN SOCIETY FOR ANALYTICAL CHEMISTRY

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  • The Society of Boron, Borides and Related Materials of Japan

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Research Projects

  • 即発ガンマ線分析を利用したホウ素材料分析の高度化

    Grant number:23K13550  2023 - 2024

    日本学術振興会  科学研究費助成事業  若手研究

    墨田 岳大

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    Authorship:Principal investigator  Grant type:Scientific research funding

    本研究では、ホウ素材料分析の高度化を目指す。
    新材料開発を推進するうえで、材料の正確な組成情報は必要不可欠である。ところが材料の機能発現の一翼を担っているホウ素においては、その定量分析の困難さから、材料中濃度が正確に定量されていない。
    そこで本研究では、即発ガンマ線分析の強みを生かして各種汎用分析手法におけるホウ素分析確度を評価する。
    本研究から得られるホウ素分析の定量確度・精度に関する知見をまとめることで、分析手法・分析機関に依らない新材料研究に貢献する。

    CiNii Research

  • 高精度かつ簡便な金属系燃料デブリ中ホウ素濃度定量法の開発

    Grant number:20K15209  2020 - 2022

    日本学術振興会  科学研究費助成事業  若手研究

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    Grant type:Scientific research funding

  • 放射線・化学・生物的作用の複合効果による燃料デブリ劣化機構の解明

    2019 - 2022

    文科省 英知を結集した原子力科学技術・人材育成推進事業(研究人材育成型廃炉研究プログラム)

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    Authorship:Coinvestigator(s)  Grant type:Contract research

  • 制御棒由来の金属融体による炉内材料破損挙動とデブリ形成挙動の解明

    2019 - 2020

    日本原子力研究開発機構 令和元年度 1F廃炉研究開発推進費

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    Authorship:Principal investigator  Grant type:Contract research

  • 沸騰水型軽水炉過酷事故時の炉内構造物溶損形態の解明

    2016 - 2017

    東京工業大学 博士課程教育リーディングプログラム 独創的教育研究経費

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    Authorship:Principal investigator  Grant type:Contract research

FD Participation

  • 2023.4   Role:Participation   Title:令和5年度 第1回全学FD(新任教員の研修)The 1st All-University FD (training for new faculty members) in FY2023

    Organizer:University-wide

Media Coverage

  • 【プレスリリース】材料が溶ける不思議“多成分系での共晶溶融現象”を解明 ―未知物質である福島第一原子力発電所の“燃料デブリ”の性状予測への第一歩―

    福島民友(2021年11月3日)、電気新聞(2021年11月4日)、日刊工業新聞(2021年11月10日)、科学新聞(2021年11月12日)  2021.11

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    【プレスリリース】材料が溶ける不思議“多成分系での共晶溶融現象”を解明 ―未知物質である福島第一原子力発電所の“燃料デブリ”の性状予測への第一歩―

  • 【プレスリリース】材料が溶ける不思議“多成分系での共晶溶融現象”を解明 ―未知物質である福島第一原子力発電所の“燃料デブリ”の性状予測への第一歩―

    福島民友(2021年11月3日)、電気新聞(2021年11月4日)、日刊工業新聞(2021年11月10日)、科学新聞(2021年11月12日)  2021.11

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    【プレスリリース】材料が溶ける不思議“多成分系での共晶溶融現象”を解明 ―未知物質である福島第一原子力発電所の“燃料デブリ”の性状予測への第一歩―

  • 未来へげんき No.61

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    未来へげんき No.61

  • 未来へげんき No.61

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    未来へげんき No.61

  • 未来へげんき No.61 Promotional material

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