Organization
Institute of Integrated Research Laboratory for Zero-Carbon Energy Associate Professor
Title
Associate Professor
External link
KONDO MASATOSHI
News & Topics
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2023/08/25
Languages： English
Fusion reactors, fast breeder reactors, and solar thermal power plants are being developed as power plants with low environmental impact and no resource constraints. Since these power plants oper
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アンカーやペグで基材にがっちり張り付くα-Al2O3被膜 核融合炉などの保護性被膜、剥がれにくくなるメカニズムを解明
2023/08/24
Languages： Japanese
要点-α-Al2O3保護性被膜の組織に、被膜の成長を促す「酸素だけが通れるトンネル」構造が形成されることを発見。-被膜成長時にアンカーやペグに似た構造を形成することで、基材から剥がれにくくなるメカニズムを解明。-核融合炉などにおいて液体金属を冷却材に用いる
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Mitigating corrosion by liquid tin could lead to better cooling in fusion reactors
2022/12/15
Languages： English
Researchers at Tokyo Institute of Technology and the National Institute for Fusion Science have clarified the chemical compatibility between high temperature liquid metal tin (Sn) and reduced
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液体金属スズで構造を保護する核融合炉機器の開発に見通し 高温の液体金属スズによる材料腐食のメカニズムと対処法を解明
2022/12/05
Languages： Japanese
要点 将来の核融合炉の先進的受熱機器である液体金属スズダイバータ開発に見通し 600℃の液体金属スズ中での核融合炉構造材の腐食メカニズムを解明 鉄やクロムの酸化物焼結体が液体金属スズに対して優れた耐食性を示すことを発見 概要東京工業大学 科学技術創成研究院 ゼロカーボンエネルギー研究所の近藤正聡准教授と工学院 機械系の宮川幸大大学院生（研究当時）、環境・社会理工学院 融合理工学系の北村嘉
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2022/03/10
Languages： English
Do two promising structural materials corrode at very high temperatures when in contact with liquid metal fuel breeders in fusion reactors? Researche
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高性能核融合炉ブランケットの新概念に見通し 900℃で機能する液体金属の合成法の開発とその腐食性に耐える構造材の発見
2022/02/24
Languages： Japanese
要点-高温の液体金属を用いることで、水素製造などもできる核融合炉発電ブランケットの高性能化へ見通し。-900℃で機能する高純度の液体リチウム鉛合金の大量合成に成功。-900℃の液体金属が生じる厳しい腐食性に耐える構造材の候補材料を発見。概要東京工業大学科学技術創成研究院ゼロカーボンエネルギー研究所の
Research Interests
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原子力、高速炉、核融合炉、液体金属
Research Areas
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Energy Engineering / Nuclear fusion
Education
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Tokyo Institute of Technology Graduate school of science and engineering Department of Nuclear Engineering
2004.4 - 2006.3
Research History
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Ministry of Education, Culture, Sports, Science and Technology (MEXT)
2022.4 - 2023.2
Country：Japan
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Tokyo Institute of Technology Institute of Innovative Research, Laboratory for Zero-Carbon Energy Associate Professor
2021.6
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文部科学省 研究開発局 学術調査官(併任)
2020.4 - 2022.3
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Tokyo Institute of Technology Institute of Innovative Research Laboratory for Advanced Nuclear Energy Associate Professor
2018.4 - 2021.5
Country：Japan
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Tokyo Institute of Technology Assistant Professor
2016.4 - 2018.3
Country：Japan
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Japan Atomic Energy Agency
2015.6 - 2016.3
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Tokyo Institute of Technology Assistant Professor
2015.4 - 2016.3
Country：Japan
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Tokai University Department of Nuclear Engineering Junior associate professor
2011.4 - 2015.3
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Doshisha University
2010.10 - 2010.11
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The Graduate University for Advanced Studies School of Physical Sciences Assistant professor
2008.4 - 2011.3
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Chubu University
2007.9 - 2008.3
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National Institute for Fusion Science Fusion Systems Research Division Assistant Professor
2006.4 - 2011.3
Committee Memberships
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核融合科学研究所研究教育改善室研究協力委員会 日米科学技術協力事業核融合分野研究計画専門部会構成員
2025.12 - 2026.3
Committee type：Other
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International Symposium on Zero-Carbon Energy Systems, IZES Steering Committee
2022.6 - 2023.6
Committee type：Other
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International Symposium on Zero-Carbon Energy Systems, IZES Technical Program Committee
2022.6 - 2023.6
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日本原子力学会 材料部会 国際学術小委員会委員
2022.4 - 2023.3
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第14回核融合エネルギー連合講演会 プログラム副委員長・実行副委員長
2021.12 - 2022.8
Committee type：Academic society
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プラズマ・核融合学会 代議員
2021.4 - 2023.3
Committee type：Academic society
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プラズマ・核融合学会 第12回核融合エネルギー連合講演会プログラム委員会委員
2017.6 - 2017.12
Committee type：Academic society
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International Advisory board
2017.6
Committee type：Academic society
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第4回セルビアセラミクス協会セラミクス材料に関する国際会議 国際アドバイザリーボード
2017.6
Committee type：Academic society
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日本原子力学会 会員サービス委員会サポートWG
2017.1
Committee type：Academic society
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核融合エネルギーフォーラム 核融合実用化若手検討会 幹事
2016.12
Committee type：Academic society
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核融合エネルギーフォーラム ITER/BA成果報告会 実行委員 （産業界と若者の意見交換会担当）
2016.10 - 2016.12
Committee type：Academic society
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東京工業大学科学技術創成研究院先導原子力研究所 アトム会 幹事
2016.4
Committee type：Other
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東京工業大学科学技術創成研究院先導原子力研究所 広報委員会委員
2016
Committee type：Other
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東京工業大学科学技術創成研究院先導原子力研究所 企画委員会委員
2016
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日本保全学会「核融合中性子の高度利用による消滅処理検討委員会(自主的分科会)」 委員
2015.12
Committee type：Academic society
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The Japan Society of Plasma Science and Nuclear Fusion Research Public relations committee, wikipedia working group
2015.11
Committee type：Academic society
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プラズマ核融合学会 広報委員会Wikipediaワーキンググループ幹事
2015.11
Committee type：Academic society
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核融合炉工学技術に関する国際シンポジウム 第13回 Local organizing committee (LOC) vice chairman
2015.9 - 2017.9
Committee type：Academic society
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International symposium for fusion technology (ISFNT) 13 Local organizing committee (LOC) vice chairman
2015.9 - 2017.9
Committee type：Academic society
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プラズマ核融合学会 男女共同参画委員会委員
2015.9 - 2016.3
Committee type：Academic society
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国立研究開発法人日本原子力研究開発機構原型炉設計合同特別チーム 核融合原型炉システム設計グループメンバー
2015.6 - 2016.3
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日本原子力学会 核融合工学部会 広報委員
2015.4
Committee type：Academic society
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東京工業大学 平成２７年度文部科学省共済組合東京工業大学支部福祉事業に関する連絡協議会委員
2015 - 2016
Committee type：Other
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日本原子力学会 プログラム編集委員（核融合炉工学分野）
2014.4 - 2016.4
Committee type：Academic society
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日本原子力学会 倫理委員会委員
2014.4
Committee type：Academic society
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文部科学省 学技術政策研究所科学技術動向研究センター調査員
2014.4
Committee type：Government
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日本原子力学会 材料部会庶務幹事
2012.4 - 2014.3
Committee type：Academic society
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プラズマ核融合学会 プラズマ核融合学会誌編集委員 (炉工学分野)
2011.7 - 2012.7
Committee type：Academic society
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東京工業大学 革新的原子力研究センターGIF-LFR専門委員会委員
2011.4
Committee type：Other
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財団法人レーザー技術総合研究所 レーザー核融合実験炉設計委員会
2011.2
Committee type：Other
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プラズマ核融合学会 プラズマ核融合学会誌編集主査 (炉工学分野)
2010.7 - 2011.7
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プラズマ核融合学会 プラズマ核融合学会誌編集委員 (炉工学分野)
2009.7 - 2010.7
Committee type：Academic society
Papers
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A methodology for corrosion testing ODS steels in liquid tin under reactor conditions in HFIR
Nick G. Russell, Marie Romedenne, Jiheon Jun, Bruce A. Pint, Masatoshi Kondo, Cansu On, Yutai Katoh
Fusion Engineering and Design 2026.1
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Reformation of protective oxide layers on artificially abraded surfaces of FeCrAl alloy during 4000 h exposure in flowing lead-bismuth eutectic
Masatoshi KONDO, Yoshiki KITAMURA, Atsushi KAWARAI, Shigeru SAITO, Hironari OBAYASHI
Corrosion Science 2026.1
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Corrosion behavior of 316L austenitic steel in liquid lithium lead alloy under stress loading conditions
Masatoshi Kondo, Yota Koike, Kenshi Ohno, Kaoru Omiya, Minho Oh, Naoko Oono-Hori
Fusion Engineering and Design 2025.7
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Experimental and analytical investigations to reduce MHD pressure drop for liquid LiPb fusion blanket systems: use of ODS-FeCrAl alloys with electrically insulating α-Al2O3 layer in optimal flow channel geometry
Ryunosuke Nishio, Masatoshi Kondo, Teruya Tanaka, Naoko Oono-Hori
Nuclear Materials and Energy 2025.7
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Toranosuke Horikawa, Mahiro Masuda, Minho Oh, Masatoshi Kondo
Water Reuse 2025.2
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Growth of α-Al2O3 layer involving abnormal oxides in FeCrAl alloy tube fabricated by WEDM process and electrical insulating performance in fusion reactor blanket
Ryuhei Muto, Masatoshi Kondo, Takashi Endo, Ryunosuke Nishio, Teruya Tanaka
Surface and Coatings Technology 493 131250 - 131250 2024.10
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Chemical and structural durability of α-Al2O3 and γ-LiAlO2 layers formed on ODS FeCrAl alloys in liquid lithium lead stirred flow
Masatoshi Kondo, Susumu Hatakeyama, Naoko Oono, Yoshiki Kitamura, Kan Sakamoto, Teruya Tanaka, Yoshimitsu Hishinuma
Corrosion Science 112459 - 112459 2024.9
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Liquid metal compatibility of pre-oxidized FeCrAl in flowing Sn
Pint, B.A., Su, Y.F., Romedenne, M., Jun, J., Kondo, M., Oono, N., Sakamoto, K., Hatano, Y.
Fusion Engineering and Design 202 2024
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Excellent adhesion of protective α-Al2O3 layer formed on ODS FeCrAl alloys
Yoshiki Kitamura, Masatoshi Kondo, Naoko Oono-Hori, Yoshimitsu Hishinuma
Surface and Coatings Technology 469 129787 - 129787 2023.9
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Ryunosuke Nishio, Teruya Tanaka, Naoko Oono, Masatoshi Kondo
Nuclear Materials and Energy 34 2023.3
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Fundamental study on optical performance of low-melting-point metal mirrors for space telescopes
Imaizumi, E., Kondo, M., Murakami, K., Hayano, Y., Matsuda, Y.
Results in Optics 12 2023
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Corrosion mechanism of reduced activation ferritic martensitic steel JLF-1 in liquid metal Sn Reviewed
Masatoshi Kondo, Miyakawa Yukihiro, Yoshiki Kitamura, Minho O, Teruya Tanaka
Corrosion Science 209 110748 - 110748 2022.12
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On-Line Measurement of Liquid Metal Level by Change of Static Gas Pressure
Ryunosuke NISHIO, Masatoshi KONDO
Plasma and Fusion Research 2022.7
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Corrosion behaviors of various steels and nickel-based alloys in liquid Sn media
Yukihiro Miyakawa, Masatoshi Kondo
Nuclear Materials and Energy Vol. 30 2022.2
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Chemical compatibility of F82H and 316L in liquid metal heat transfer mediums Li, Na and NaK
Tatsuhiro Hosaka, Masatoshi Kondo, Satoshi Sato, Masami Ando, Takashi Nozawa
Journal of Nuclear Materials Vol. 561 ( No. 153546 ) 2022.1
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Self-Healing Behavior of Oxide Layer in Liquid Metal*)
Kawarai, A., Kondo, M.
Plasma and Fusion Research 17 2022
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Effect of Temperature on Fretting Corrosion Behaviors between Li2TiO3 Pebble and F82H
Masaki, H., Kondo, M., Kim, J.-H., Nakamichi, M.
Plasma and Fusion Research 17 2022
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Corrosion-resistant materials for liquid LiPb fusion blanket in elevated temperature operation
Masatoshi Kondo, Susumu Hatakeyama, Naoko Oono, Takashi Nozawa
Corrosion Science Vol. 197 2021.12
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Dense-film preparation of zirconium oxide by self-oxidation in air
Rio Takemura, Kiyoto Shin-mura, Kazuya Sasaki, Eiki Niwa, Masatoshi Kondo
Fusion Engineering and Design Vol. 171 2021.7
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オンライン座談会：産業界と“超”若者の意見交換会 〈私たちの未来はどうなる 高校生が作る未来マップ〉
近藤正聡
プラズマ・核融合学会誌 2021.6
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Kondo, M., Pint, B.A., Jun, J., Russell, N., Mcduffee, J., Akiyoshi, M., Tanaka, T., Oono, N., Miyazawa, J., Geringer, J.W., Katoh, Y., Hatano, Y.
Plasma and Fusion Research 16 ( 0 ) 2905088 - 2905088 2021.6
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Fundamental Study on Fretting Corrosion in Solid Breeder Blanket
Naoki TAKAHASHI, Masatoshi KONDO, Jae-Hwan KIM, Masaru NAKAMICHI
Plasma and Fusion Research Vol. 16 2021.4
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Conceptual Design of HFIR Irradiation Experiment for Material Compatibility Study on Liquid Sn Divertor
Masatoshi KONDO, Bruce A. PINT, Jiheon JUN, Nick RUSSELL, Joel McDUFFEE, Masafumi AKIYOSHI, Teruya TANAKA, Naoko OONO, Junichi MIYAZAWA, Josina W GERINGER, Yutai KATO, Yuji HATANO
Plasma and Fusion Research Vol. 16 2405040 - 2405040 2021.4
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Mass Transfer of Ni in Liquid Li Detected by Quartz Crystal Microbalance
Leo IIZUKA, Masatoshi KONDO
Plasma and Fusion Research Vol. 16 2021.3
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Novel Cleaning Methodologies for Specimens Tested in Liquid Metals
Susumu HATAKEYAMA, Naoko OONO, Takashi NOZAWA, Kan SAKAMOTO, Yoshie TAMAI, Masatoshi KONDO
Plasma and Fusion Research Volume 16 1205015 - 1205015 2021.2
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サロン コロナ禍で核融合炉を学ぶ学生は何を思うのか: コロナウイルス感染症に負けるな! 核融合若手インフォーマルミーティング主催, 緊急特別企画リモートセミナーの開催報告
Masatoshi KONDO
プラズマ・核融合学会誌= Journal of plasma and fusion research 2020.9
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Materials issues for liquid metal coolant nuclear systems
T. Muroga, M. Kondo
Challenges for Coolants in Fast Neutron Spectrum Systems 2020.5
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Material issues related to tritium breeding and energy conversion in inertial fusion reactors
M. Kondo, K. Yamanoi, T. Norimatsu
Pathways to Energy from Inertial Fusion: Structural Materials for Inertial Fusion Facilities Vol. 1911 2020.5
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波多野雄治, 横峯健彦, 檜木達也, 橋本直幸, 大矢恭久, 大塚哲平, 近藤正聡, 宮沢順一, 長坂琢也
プラズマ核融合学会誌 2020.3
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Liquid BreederMaterials Reviewed
Masatoshi Kondo, Teruya Tanaka, Satoshi Fukada, Tsusar Valentyn
Comprehensive Nuclear Materials 2nd edition, Reference Module in Materials Science and Materials Engineering 2020 2020.3
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FRONTIER 計画 (2019 年度̃ 2024 年度)(プロジェクトレビュー 日米科学技術協力事業 PHENIX 計画: 6 年間の成果と次期計画)
Masatoshi KONDO
プラズマ・核融合学会誌= Journal of plasma and fusion research 2020
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A. 7 Material Compatibility Study on Liquid Metal Divertor of Fusion Reactors
Kondo, Masatoshi
I. Special Articles in Commemoration of Retiring Professors 20 - 20 2020
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Excellent Corrosion Resistance of Tungsten Materials in liquid Tin
Kawano, Nanako, Tamai, Yoshie, Kondo, Masatoshi
Plasma and Fusion Research 15 1205068 - 1205068 2020
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座談会：原型炉時代の産業界と若手をつなぐ交流の懸け橋 Reviewed
プラズマ・核融合学会誌 2019.8
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ボードゲームの中の原型炉建設と研究者の多様性 Reviewed
プラズマ・核融合学会誌 2019.5
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Corrosion resistance of Al-rich steel and Al2O3 ceramic bulk in liquid Sn Reviewed
Masatoshi Kondo, Masaru Tada, Youko Ohtsuka, Yoshimitsu Hishinuma, Takeo Muroga
Fusion Engineering and Design 146 2450 - 2456 2019.4
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Conference report on the 1st US--Japan workshop on power and particle control by liquid metal plasma-facing components in a steady state magnetic fusion DEMO reactor
Hirooka, Yoshi, Ono, Masayuki, Maingi, Rajesh, Hanada, Kazuaki, Kondo, Masatoshi, Miyazawa, Junichi, Shimada, Michiya
Nuclear Fusion 60 ( 1 ) 017001 - 017001 2019
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もっとも多くダウンロードされた記事はこちら!
Masatoshi KONDO
Journal of Plasma and Fusion Research 2019
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Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
Takashi Nozawa, Kazumi Ozawa, Chang Ho Park, Joon Soo Park, Akira Kohyama, Akira Hasegawa, Shuhei Nogami, Tatsuya Hinoki, Sosuke Kondo, Toyohiko Yano, Tamaki Shibayama, Bun Tsuchiya, Tatsuo Shikama, Shinji Nagata, Teruya Tanaka, Hirotomo Iwakiri, Yasushi Yamamoto, Satoshi Konishi, Ryuta Kasada, Masatoshi Kondo, Tomoaki Kunugi, Takehiko Yokomine, Yoshitaka Ueki, Nariaki Okubo, Tomitsugu Taguchi, Hiroyasu Tanigawa
Journal of Nuclear Materials 511 582 - 590 2018.12
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核融合トリチウム研究最前線―原型炉実現に向けて―第5 回液体増殖材開発の最前線 Reviewed
2018.11
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Effect of isotope enrichment on performance of lead-lithium blanket of inertial fusion reactor Reviewed
Masatoshi Kondo, Yuu Nakajima, Teruya Tanaka, Takayoshi Norimatsu
IOP Conf. Series: Journal of Physics: Conf. Series Vol. 1090 ( No. Conference 1 ) 2018.9
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Masatoshi Kondo, Yoshimitsu Hishinuma, Takayoshi Norimatsu, Takeo Muroga
Fusion Engineering and Design 136 1581 - 1587 2018.5
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Research frontier of tritium for fusion reactor. Toward the DEMO reactor (5). Research frontiers of liquid breeders for fusion reactors
Kondo, Masatoshi, Tanaka, Teruya
Nippon Genshiryoku Gakkai-Shi (Atomos) 60 ( 11 ) 700 - 704 2018
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Pribadi adhi, Nariaki Okubo, Atushi Komatsu, Masatoshi Kondo, Minoru Takahashi
Energy Procedia Vol. 131 2017.12
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Oxidation characteristics of lead-alloy coolants in air ingress accident Reviewed
Masatoshi kondo, Nariaki Okubo, Eriko Irisawa, Atsushi Komatsu, Norito Ishikawa, Teruya Tanaka
Energy procedia Vol. 131 2017.12
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Teruya Tanaka, Daiji Kato, Takashi Nozawa, Bun Tsuchiya, Masatoshi Kondo, Takeo Muroga
Fusion Engineering and Design 2017.5
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溶融鉛環境下の溶存酸素濃度と酸化物被覆健全性の同時モニタリングに関する研究 Reviewed
日本機械学会論文集 Vol. 83 ( No. 847 ) 2017.3
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Performance of solid electrolyte oxygen sensor with solid and liquid reference electrode for liquid metal Reviewed
Adhi, Pribadi Mumpuni, Kondo, Masatoshi, Takahashi, Minoru
Sensors and Actuators B-Chemical 241 2017
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Metallurgical study on corrosion of RAFM steel JLF-1 in Pb-Li alloys with various Li concentrations Reviewed
Masatoshi Kondo, Masaomi Ishii, Yoshimitsu Hishinuma, Teruya Tanaka, Takashi Nozawa, Takeo Muroga
Fusion Engineering and Design Vol. 125 2017
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On-line monitoring of oxygen potential and structure of oxide layer in liquid metals by electrochemical methods
Kondo, Masatoshi, Takahashi, Minoru and Adhi, Pribadi Mumpuni, Suzuki, Narumi, Matsumura, Yoshihito, Tanaka, Teruya, Hishinuma, Yoshimitsu, Sagara, Akio, Muroga, Takeo
Nippon Kikai Gakkai Ronbunshu (Online) 83 ( 847 ) 16 - 00412 2017
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Study on performance of oxygen sensors with solid and liquid reference electrodes in liquid LBE with the parameters of oxygen potential and temperature
Adhia, Pribadi Mumpuni, Kondob, Masatoshi, Takahashib, Minoru
relation 2 2 - 2 2017
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Experimental study on corrosion and precipitation in non-isothermal Pb-17Li system for development of liquid breeder blanket of fusion reactor Reviewed
Kondo, Masatoshi, Ishii, Masaomi, Norimatsu, Takayoshi, Muroga, Takeo
International Conference on Energy Sciences (Ices 2016) 877 2017
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A. 5 Chemical behaviors of lead-alloy coolants in air ingress accident
Kondo, Masatoshi
I. Special Articles in Commemoration of Retiring Professors 18 - 18 2017
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Evaluation of thermal conductivity for liquid lead lithium alloys at various Li concentrations based on measurement and evaluation of density, thermal diffusivity and specific heat of alloys Reviewed
Masatoshi Kondo, Yuu Nakajima, Mitsuyo Tsuji, Takashi Nozawa
FUSION ENGINEERING AND DESIGN 109 1345 - 1350 2016.11
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高速スペクトル原子炉 (18章 鉛冷却原子炉担当)
近藤正聡
2016.10
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Evaluation of thermophysical and chemical characteristics of lithium lead alloys for development of self-cooled type liquid breeder blanket systems
Kondo, Masatoshi
Bulletin of the Research Laboratory for Nuclear Reactors (Tokyo Institute of Technology) 39 51 - 53 2016
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Conceptual design of temporally storage area in hot cell for fusion DEMO reactor Reviewed
Masatoshi Kondo, Youji Someya, Mitsuyo Tsuji, Satoshi Yanagihara, Hiroyasu Utoh, Takashi Kato, Kenji Tobita, Shinzaburo Matsuda
Plasma and Fusion Research 11 ( 1 ) 2016
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In-Situ Evaluation of Functional Layer Based on Impedance Behavior
Suzuki, Narumi, Ryosuke, Sasaki, Matsumura, Yoshihito, Kondo, Masatoshi
Journal of the Japan Institute of Metals 80 ( 9 ) 585 - 592 2016
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Compatibility issues for liquid breeders and liquid divertor for fusion reactors
Kondo, Masatoshi, Nagasaka, Takuya
Purazuma, Kaku Yugo Gakkai-Shi 92 ( 2 ) 130 - 135 2016
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In-Situ Evaluation of Functional Layer by Electrochemical Impedance Spectroscopy Reviewed
Narumi Suzuki, Ryosuke Sasaki, Yoshihito Matsumura, Masatoshi Kondo
JOURNAL OF THE JAPAN INSTITUTE OF METALS 80 ( 4 ) 284 - 288 2016
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液体だけど水じゃない-次世代ブランケット・ダイバータ研究開発の現状と課題-5. 液体燃料増殖材及び液体ダイバータ冷却材の共存性 Reviewed
近藤正聡, 長坂琢也
プラズマ・核融合学会誌第 92 巻第 2 号 92 ( 2 ) 130 - 135 2016
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STUDY ON STABILITY OF LIQUID JET FOR LIQUID LITHIUM TARGET OF BORON NEUTRON CAPTURE THERAPY (BNCT) Reviewed
Yuki Maehara, Masatoshi Kondo, Minoru Takahashi
PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 5 2016
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Experimental study on chemical behaviors of non-metal impurities in Pb, Pb-Bi and Pb-Li by temperature programmed desorption mass spectrometer analysis Reviewed
Masatoshi Kondo, Yuu Nakajima, Teruya Tanaka, Takashi Nozawa, Takehiko Yokomine
Plasma and Fusion Research 11 ( 1 ) 2016
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機能性被覆の性状とインピーダンス応答の関係を用いた in-situ 評価 Reviewed
鈴木成実, 佐々木亮佑, 松村義人, 近藤正聡
講演概要集 80 ( 9 ) 585 - 592 2016
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Corrosion of steels in molten gallium (Ga), tin (Sn) and tin lithium alloy (Sn-20Li) Reviewed
Masatoshi Kondo, Masaorni Ishii, Takeo Muroga
FUSION ENGINEERING AND DESIGN 98-99 2003 - 2008 2015.10
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Study on fabrication method of lithium alloys with metal grains Reviewed
Yuu Nakajima, Masatoshi Kondo, Takashi Nozawa
FUSION ENGINEERING AND DESIGN 98-99 2009 - 2014 2015.10
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Study on fabrication method of lithium alloys with metal grains Reviewed
Yuu Nakajima, Masatoshi Kondo, Takashi Nozawa
FUSION ENGINEERING AND DESIGN 98-99 2009 - 2014 2015.10
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Corrosion Resistance of High Cr Steels and Ceramic Materials in Lead-Bismuth Flow
Kondo, Masatoshi
International Conference Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005), Paper No. 425 2015
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Design study on double layer type interface structure for heat exchanger of Fusion DEMO blanket
Kondo, Masatoshi, Tanaka, Teruya, Hishinuma, Yoshimitsu, Suzuki, Narumi, Kawamata, Yosuke, Chikaraishi, H., Muroga, Takeo, Sagara, Akio
Book of Abstracts 2015
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Corrosion Resistance of High Cr Steels and Ceramic Materials in Lead-Bismuth Flow
Kondo, Masatoshi
International Conference Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005), Paper No. 425 2015
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Evaluation of density and thermal diffusivity of liquid Pb-Li alloys at various Li concentrations
KONDO, Masatoshi, Nakajima, Yuu, Tsuji, Mitsuyo, Nozawa, Takashi
Book of abstract 2015
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Desorption of non-metal impurities from Pb and Pb-Li alloy
KONDO, Masatoshi, Nakajima, Yuu, Tanaka, Teruya, Nozawa, Takashi, Yokomine, Takehiko
Desorption of non-metal impurities from Pb and Pb-Li alloy 2015
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Desorption of non-metal impurities from Pb and Pb-Li alloy
KONDO, Masatoshi, Nakajima, Yuu, Tanaka, Teruya, Nozawa, Takashi, Yokomine, Takehiko
Desorption of non-metal impurities from Pb and Pb-Li alloy 2015
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Design study on double layer type interface structure for heat exchanger of Fusion DEMO blanket
Kondo, Masatoshi, Tanaka, Teruya, Hishinuma, Yoshimitsu, Suzuki, Narumi, Kawamata, Yosuke, Chikaraishi, H., Muroga, Takeo, Sagara, Akio
Book of Abstracts 2015
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液体ブランケットの熱交換器界面構造改善に関する研究 Reviewed
川俣陽平, 中嶋結, 鈴木成実, 近藤正聡, 田中照也, 菱沼良光, 力石浩孝, 室賀健夫, 相良明男
日本原子力学会 2015 年 春の年会 学生セッション 予稿集 2015
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電気化学インピーダンス法を用いた機能性被覆の定常診断法 Reviewed
鈴木成実, 近藤正聡, 田中照也
日本原子力学会 2015 年 春の年会 学生セッション 予稿集 2015
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高温酸化による機能性被覆形成挙動の解明と電気特性評価 Reviewed
鈴木成実, 近藤正聡, 田中照也
高温酸化による機能性被覆形成挙動の解明と電気特性評価 2015
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核融合原型炉のメンテナンス施設の設計検討 Reviewed
辻光世, 近藤正聡, 染谷洋二
核融合原型炉のメンテナンス施設の設計検討 2015
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リチウム合金環境中における低放射化フェライト鋼の共存性に関する評価 Reviewed
石井政臣, 近藤正聡, 室賀健夫
日本原子力学会 2015 年 春の年会 学生セッション 予稿集 2015
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原子力・量子・核融合事典 第 1 分冊 5.4. 3 「冷却材との両立」
近藤正聡
原子力・量子・核融合事典 第 1 分冊 5.4. 3 「冷却材との両立」 2014.10
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Electrochemical impedance spectroscopy on in-situ analysis of oxide layer formation in liquid metal Reviewed
M. Kondo, N. Suzuki, Y. Nakajima, T. Tanaka, T. Muroga
FUSION ENGINEERING AND DESIGN 89 ( 7-8 ) 1201 - 1208 2014.10
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Waste management scenario in the hot cell and waste storage for DEMO Reviewed
Youji Someya, Kenji Tobita, Satoshi Yanagihara, Masatoshi Kondo, Hiroyasu Utoh, Nobuyuki Asakura, Kazuo Hoshino, Makoto Nakamura, Yoshiteru Sakamoto
FUSION ENGINEERING AND DESIGN 89 ( 9-10 ) 2033 - 2037 2014.10
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In-situ impedance measurement of corrosion interface in liquid metals, Fusion Engineering and Design
Masatoshi Kondo, Narumi Suzuki, Yuu Nakajima, Teruya Tanaka, Takeo Muroga
Fusion Engineering and Design Vol. 89 1201 - 1208 2014.5
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Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system
Kondo, Masatoshi, Ishii, Masaomi, Muroga, Takeo
Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system 2014
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Application of electrochemical impedance spectroscopy to in-situ corrosion monitoring of ceramic coatings in liquid breeder blanket
Kondo, Masatoshi, Suzuki, Narumi, Nakajima, Yuu, Akiyama, Yuya, Tanaka, Teruya, Hishinuma, Yoshimitsu, Muroga, Takeo, Sagara, Akio
Book of Abstracts, Numat 2014 2014
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Corrosion of steels in molten tin (Sn) and tin lithium alloy (Sn-Li)
Kondo, Masatoshi, Ishii, Masaomi, Muroga, Takeo
Book of Abstracts, 28th Symposium on Fusion Technology 2014
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Corrosion of RAFM steel JLF-1 in flowing Pb-Li alloy with and without temperature gradient
KONDO, Masatoshi, Masaomi, ISHI, MUROGA, Takeo
Book of Abstracts, Numat 2014 2014
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Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system
Kondo, Masatoshi, Ishii, Masaomi, Muroga, Takeo
Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system 2014
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Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system
Kondo, Masatoshi, Ishii, Masaomi, Muroga, Takeo
Accelerated corrosion of reduced activation ferritic martensitic steel in non-isothermal Pb-17Li system 2014
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Application of electrochemical impedance spectroscopy to in-situ corrosion monitoring of ceramic coatings in liquid breeder blanket
Kondo, Masatoshi, Suzuki, Narumi, Nakajima, Yuu, Akiyama, Yuya, Tanaka, Teruya, Hishinuma, Yoshimitsu, Muroga, Takeo, Sagara, Akio
Book of Abstracts, Numat 2014 2014
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Corrosion of RAFM steel JLF-1 in flowing Pb-Li alloy with and without temperature gradient
KONDO, Masatoshi, Masaomi, ISHI, MUROGA, Takeo
Book of Abstracts, Numat 2014 2014
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Fabrication of lithium lead alloy and impurity control by temperature-programmed desorption
Kondo, Masatoshi, Nakajima, Yuu, Tanaka, Teruya, Nozawa, Takashi, Yokomine, Takehiko
Fabrication of lithium lead alloy and impurity control by temperature-programmed desorption 2014
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Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis
SUZUKI, Narumi, KONDO, Masatoshi, TANAKA, Teruya
Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis 2014
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Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis
SUZUKI, Narumi, KONDO, Masatoshi, TANAKA, Teruya
Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis 2014
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Fabrication of lithium lead alloy and impurity control by temperature‐programmed desorption
Kondo, Masatoshi, Nakajima, Yuu, Tanaka, Teruya, Nozawa, Takashi, Yokomine, Takehiko
Fabrication of lithium lead alloy and impurity control by temperature‐programmed desorption 2014
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Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis
SUZUKI, Narumi, KONDO, Masatoshi, TANAKA, Teruya
Formation of functional layer structure by pre-oxidation process and in-situ evaluation of layer structure by EIS analysis 2014
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Fabrication of lithium lead alloy and impurity control by temperature‐programmed desorption
Kondo, Masatoshi, Nakajima, Yuu, Tanaka, Teruya, Nozawa, Takashi, Yokomine, Takehiko
Fabrication of lithium lead alloy and impurity control by temperature‐programmed desorption 2014
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Corrosion of steels in molten tin (Sn) and tin lithium alloy (Sn-Li)
Kondo, Masatoshi, Ishii, Masaomi, Muroga, Takeo
Book of Abstracts, 28th Symposium on Fusion Technology 2014
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Corrosion of RAFM steel JLF-1 in flowing Pb-Li alloy with and without temperature gradient
KONDO, Masatoshi, Masaomi, ISHI, MUROGA, Takeo
Book of Abstracts, Numat 2014 2014
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Corrosion behavior of 9Cr-ODS steel in stagnant liquid lithium and lead-lithium at 873 K Reviewed
Yanfen Li, Hiroaki Abe, Takuya Nagasaka, Takeo Muroga, Masatoshi Kondo
JOURNAL OF NUCLEAR MATERIALS 443 ( 1-3 ) 200 - 206 2013.11
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Boiling points of liquid breeders for fusion blankets Reviewed
Masatoshi Kondo, Yuu Nakajima
FUSION ENGINEERING AND DESIGN 88 ( 9-10 ) 2556 - 2559 2013.10
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Heat-pulse flow meter for liquid breeders
Kondo, Masatoshi, Shibano, Kyohei
Plasma and Fusion Research and Nuclear Fusion Research 8 1 - 6 2013
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Study on fabrication method of lithium alloys and impurity control
Kondo, Masatoshi, Nakajima, Yuu, Suzuki, Narumi
Book of Abstracts, APFA2013 2013
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Study on fabrication method of lithium alloys and impurity control
Kondo, Masatoshi, Nakajima, Yuu, Suzuki, Narumi
Book of Abstracts, APFA2013 2013
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Study on fabrication method of lithium alloys and impurity control
Kondo, Masatoshi, Nakajima, Yuu, Suzuki, Narumi
Book of Abstracts, APFA2013 2013
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Activities in CRINES for Generation IV International Forum, Lead-cooled Fast Reactor
TAKAHASHI, Minoru, OBARA, Toru, MINATO, Akio, UCHIDA, Shoji, KIKUCHI, Kenji, KONDO, Masatoshi, NAGATA, Akito
Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4) 11 - 3 2013
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Effect of isotope enrichment on tritium breeding and suppression of polonium formation in lithium lead blanket
KONDO, Masatoshi, Nakajima, Yuu, Norimatsu, Takayoshi
Book of Abstracts, APFA2013 2013
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Activities in CRINES for Generation IV International Forum, Lead-cooled Fast Reactor
TAKAHASHI, Minoru, OBARA, Toru, MINATO, Akio, UCHIDA, Shoji, KIKUCHI, Kenji, KONDO, Masatoshi, NAGATA, Akito
Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4) 2013
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Effect of isotope enrichment on tritium breeding and suppression of polonium formation in lithium lead blanket
KONDO, Masatoshi, Nakajima, Yuu, Norimatsu, Takayoshi
Book of Abstracts, APFA2013 2013
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Electrochemical impedance measurement of oxide film with liquid metal electrode of lead lithium alloy
Kondo, Masatoshi, Akiyama, Yuya, Tanaka, Teruya, Suzuki, Narumi, Nakajima, Yuu
Book of Abstracts, APFA2013 2013
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Electrochemical impedance measurement of oxide film with liquid metal electrode of lead lithium alloy
Kondo, Masatoshi, Akiyama, Yuya, Tanaka, Teruya, Suzuki, Narumi, Nakajima, Yuu
Book of Abstracts, APFA2013 2013
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Effect of isotope enrichment on tritium breeding and suppression of polonium formation in lithium lead blanket
KONDO, Masatoshi, Nakajima, Yuu, Norimatsu, Takayoshi
Book of Abstracts, APFA2013 2013
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Corrosion characteristics of RAFM steels and unalloyed metals in static Pb-17Li Reviewed
Takeo Muroga, Masatoshi Kondo
Plasma and Fusion Research 8 ( 2 ) 2013
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Heat-Pulse Flowmeter for a Liquid Breeder Blanket
KONDO Masatoshi, SHIBANO Kyohei, TANAKA Teruya, MUROGA Takeo
Plasma and Fusion Research 8 2405086 - 2405086 2013
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Hydrogen transport through interface between gas bubbling and liquid breeders Reviewed
Masatoshi Kondo, Tomoko Oshima, Masahiro Tanaka, Takeo Muroga, Akio Sagara
FUSION ENGINEERING AND DESIGN 87 ( 10 ) 1788 - 1793 2012.10
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Masatoshi Kondo, Minoru Takahashi, Teruya Tanaka, Valentyn Tsisar, Takeo Muroga
FUSION ENGINEERING AND DESIGN 87 ( 10 ) 1777 - 1787 2012.10
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Valentyn Tsisar, Masatoshi Kondo, Takeo Muroga, Takuya Nagasaka, Izuru Matushita
FUSION ENGINEERING AND DESIGN 87 ( 4 ) 363 - 368 2012.5
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Fabrication of the hydrogen recovery unit in the molten salt loop orosh2I-1 and preliminary evaluation for hydrogen transfer Reviewed
Takuya Nagasaka, Teruya Tanaka, Akio Sagara, Teruo Muroga, Masatoshi Kondo, Takashi Watanabe, Satoshi Fukada, Hiroshi Yukawa, Tomonori Nambu, Tomohito Iikubo
Plasma and Fusion Research 7 ( 1 ) 2012
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Electroplating of erbium on steel surface in ErCl3 Doped LiCl-KCl Reviewed
Masatoshi Kondo, Teruya Tanaka, Takeo Muroga, Hiroyuki Tsujimura, Yasuhiko Ito
Plasma and Fusion Research 7 ( 1 ) 2012
-
Nitriding of 316 stainless steel in molten fluoride salt by an electrochemical technique Reviewed
Takashi Watanabe, Masatoshi Kondo, Akio Sagara
ELECTROCHIMICA ACTA 58 681 - 690 2011.12
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Effect of nitrogen on the corrosion behavior of RAFM JLF-1 steel in lithium Reviewed
Valentyn Tsisar, Masatoshi Kondo, Qi Xu, Takeo Muroga, Takuya Nagasaka, Olga Yeliseyeva
JOURNAL OF NUCLEAR MATERIALS 417 ( 1-3 ) 1205 - 1209 2011.10
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Mass transfer of RAFM steel in Li by simple immersion, impeller induced flow and thermal convection Reviewed
Masatoshi Kondo, Takeo Muroga, Takuya Nagasaka, Qi Xu, Valentyn Tsisar, Tomoko Oshima
JOURNAL OF NUCLEAR MATERIALS 417 ( 1-3 ) 1200 - 1204 2011.10
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Compatibility of dip-coated Er2O3 coating by MOD method with liquid Li Reviewed
Dongxun Zhang, Masatoshi Kondo, Teruya Tanaka, Takeb Muroga, Tsisar Valentyn
FUSION ENGINEERING AND DESIGN 86 ( 9-11 ) 2508 - 2511 2011.10
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Flow accelerated corrosion and erosion-corrosion of RAFM steel in liquid breeders Reviewed
Masatoshi Kondo, Takeo Muroga, Akio Sagara, Tsisar Valentyn, Akihiro Suzuki, Takayuki Terai, Minoru Takahashi, Naoki Fujii, Yukihiro Yokoyama, Hiroshi Miyamoto, Eiji Nakamura
FUSION ENGINEERING AND DESIGN 86 ( 9-11 ) 2500 - 2503 2011.10
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Corrosion resistance of ceramics SiC and Si3N4 in flowing lead-bismuth eutectic Reviewed
Minoru Takahashi, Masatoshi Kondo
PROGRESS IN NUCLEAR ENERGY 53 ( 7 ) 1061 - 1065 2011.9
-
Y. F. Li, M. Kondo, T. Nagasaka, T. Muroga, V. Tsisar
FUSION SCIENCE AND TECHNOLOGY 60 ( 1 ) 359 - 363 2011.7
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Valentyn Tsisar, Masatoshi Kondo, Takeo Muroga, Takuya Nagasaka, Olga Yeliseyeva
CORROSION SCIENCE 53 ( 1 ) 441 - 447 2011.1
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日本原子力学会誌日本原子力学会誌 40, 878, 1998
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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Mechanical properties of V-4Cr-4Ti after exposure in static lithium at 650° C
Zheng, Pengfei, Nagasaka, Takuya, Muroga, Takeo, Kondo, Masatoshi, Chen, Jiming
Plasma and Fusion Research 6 2405121 - 2405121 2011
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Mechanical properties of V-4Cr-4Ti after exposure in static lithium at 650°C
Zheng, P., Nagasaka, T., Muroga, T., Kondo, M., Chen, J.
Plasma and Fusion Research 6 ( 1 SPECIAL ISSUE ) 2011
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工業レアメタル工業レアメタル, 2007
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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エコインダストリエコインダストリ 10, 25, 2005
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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エネルギー 資源エネルギー 資源 23, 125, 2002
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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鉱物資源の現状鉱物資源の現状 185, 1989
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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化学工業化学工業 50, 366, 1999
Masatoshi KONDO
プラズマ・核融合学会誌 2011
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Incretin enhancer: sitagliptin
Kondo, Manabu, Tanizawa, Yukio
Nihon rinsho. Japanese journal of clinical medicine 69 ( 5 ) 859 - 863 2011
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Mechanical properties of V-4Cr-4Ti after exposure in static lithium at 650° C
Zheng, Pengfei, Nagasaka, Takuya, Muroga, Takeo, Kondo, Masatoshi, Chen, Jiming
Plasma and Fusion Research 6 2405121 - 2405121 2011
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Mechanical properties of V-4Cr-4Ti after exposure in static lithium at 650° C
Zheng, Pengfei, Nagasaka, Takuya, Muroga, Takeo, Kondo, Masatoshi, Chen, Jiming
Plasma and Fusion Research 6 2405121 - 2405121 2011
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KONDO Masatoshi, WATANABE Takashi, TANAKA Teruya, ZHANG Dongxun, SAGARA Akio
Plasma and Fusion Research 6 2405117 - 2405117 2011
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Corrosion Characteristics of Hydrogen Permeation Materials in Molten Salt Flinak
NAGASAKA Takuya, KONDO Masatoshi, SAGARA Akio, MUROGA Takeo
Plasma and Fusion Research 6 1405146 - 1405146 2011
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Hydrogen transport in molten salt Flinak measured by solid electrolyte sensors with Pd electrode Reviewed
T. Ohshima, M. Kondo, M. Tanaka, T. Muroga, A. Sagara
FUSION ENGINEERING AND DESIGN 85 ( 10-12 ) 1841 - 1846 2010.12
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Takuya Nagasaka, Masatoshi Kondo, Takeo Muroga, Akio Sagara, Osamu Motojima, Tatsuya Tsutsumi, Tatsuya Oishi
FUSION ENGINEERING AND DESIGN 85 ( 7-9 ) 1261 - 1265 2010.12
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Masatoshi Kondo, Takuya Nagasaka, Valentyn Tsisar, Akio Sagara, Takeo Muroga, Takashi Watanabe, Tomoko Oshima, Yukihiro Yokoyama, Hiroshi Miyamoto, Eiji Nakamura, Naoki Fujii
FUSION ENGINEERING AND DESIGN 85 ( 7-9 ) 1430 - 1436 2010.12
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Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor
Qunying HUANG, Sheng GAO, ZhiqiangZHU, Zhihui GUO, Xinzhen LING, ZilinYAN, Masatoshi KONDO, Valentyn TSISAR, Takeo MUROGA, Yican WU
Advances in Science and Technology Vol. 73 2010.10
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Erosion-corrosion of RAFM JLF-1 steel in lithium flow induced by impeller
Masatoshi KONDO, Valentyn TSISAR, Takeo MUROGA, Takuya NAGASAKA, Olga YELISEYEVA
J. Plasma Fusion Res. Series Vol. 9 294 - 294 2010.8
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Corrosion characteristic of AlN, Y2O3, Er2O3 and Al2O3 in Flinak for molten salt blanket system
Watanabe, Takashi, Kondo, Masatoshi a, Nagasaka, Takuya, Sagara, Akio
Plasma and Fusion Research Vol. 9 2010.4
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Phase-structural transformations in the RAF/M, F/M and model F/ODS steels exposed to lithium-corrosion induced coarsening of substructure and effect of alloying elements
TSISAR, Valentyn, KONDO, Masatoshi, MUROGA, Takeo, NAGASAKA, Takuya, YELISEYEVA, Olga
Corrosion Science 53 2010
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Corrosion characteristic of AlN, Y ${$sub 2$}$ O ${$sub 3$}$, Er ${$sub 2$}$ O ${$sub 3$}$ and Al ${$sub 2$}$ O ${$sub 3$}$ in Flinak for molten salt blanket system
Watanabe, Takashi, Kondo, Masatoshi a, Nagasaka, Takuya, Sagara, Akio
Journal of Plasma and Fusion Research SERIES 9 2010
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Compatibility of materials with liquid metal Pb-17Li. Compatibility of reduced activation ferritic/martensitic steel in Pb-17Li
Takahashi, Minoru, Kondo, Masatoshi
Purazuma, Kaku Yugo Gakkai-Shi 86 ( 7 ) 2010
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Effort on lithium compatibility study toward happy ending
Kondo, Masatoshi, Tsisar, Valentyn, Terai, Takayuki, Suzuki, Akihiro
2010
-
Effort on lithium compatibility study toward happy ending
Kondo, Masatoshi, Tsisar, Valentyn, Terai, Takayuki, Suzuki, Akihiro
2010
-
Compatibility of materials with liquid metal Pb-17Li. Compatibility of reduced activation ferritic/martensitic steel in Pb-17Li
Takahashi, Minoru, Kondo, Masatoshi
Purazuma, Kaku Yugo Gakkai-Shi 86 ( 7 ) 2010
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伝熱工学資料伝熱工学資料, 1991
Masatoshi KONDO
プラズマ・核融合学会誌 2010
-
Technology for compatibility study for fusion blanket system
Kondo, Masatoshi, Tsisar, Valentyn, Hirose, Takanori, Seki, Yohji
Purazuma, Kaku Yugo Gakkai-Shi 86 2010
-
Wolfram syndrome 1 gene (wfs1) product localizes to insulin granule in mouse pancreatic beta cells: OP3-1
Hatanaka, M., Tababe, K., Ohta, Y., Yanai, A., Akiyama, M., Kondo, M., Shinoda, K., Oka, Y., Tanizawa, Y.
Journal Of Diabetes Investigation 1 2010
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Manuscript submission and review system will be unavailable due to a scheduled maintenance from 8: 00AM to 12: 00PM February 2, 2020 (JST).
Energy, Inertial Fusion
Plasma and Fusion Research 5 2010
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Oxidation in molten fluoride salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Suzuki, Akihiro, Terai, Takayuki
Purazuma, Kaku Yugo Gakkai-Shi 86 2010
-
Phase-structural transformations in the RAF/M, F/M and model F/ODS steels exposed to lithium-corrosion induced coarsening of substructure and effect of alloying elements
TSISAR, Valentyn, KONDO, Masatoshi, MUROGA, Takeo, NAGASAKA, Takuya, YELISEYEVA, Olga
Corrosion Science 53 2010
-
Oxidation in molten fluoride salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Suzuki, Akihiro, Terai, Takayuki
2010
-
Effort on lithium compatibility study toward happy ending
Kondo, Masatoshi, Tsisar, Valentyn, Terai, Takayuki, Suzuki, Akihiro
Purazuma, Kaku Yugo Gakkai-Shi 86 2010
-
Oxidation in molten fluoride salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Suzuki, Akihiro, Terai, Takayuki
2010
-
Consideration of Alumina Coating Fabricated by Sol-Gel Method for PbLi Flow Reviewed
Yoshitaka Ueki, Tomoaki Kunugi, Masatoshi Kondo, Akio Sagara, Neil B. Morley, Mohamed A. Abdou
Green Energy and Technology 44 373 - 379 2010
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Study of Pd Membrane Electrode in Solid Electrolyte Hydrogen (Isotopes) Sensor for Application to Liquid Blankets
OHSHIMA Tomoko, KONDO Masatoshi, TANAKA Masahiro, MUROGA Takeo
Plasma and Fusion Research 5 S1034 - S1034 2010
-
Qi Xu, Masatoshi Kondo, Takuya Nagasaka, Takeo Muroga, Olga Yeliseyeva
JOURNAL OF NUCLEAR MATERIALS 394 ( 1 ) 20 - 25 2009.10
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CHARACTERIZATION OF LIQUID LITHIUM BLANKET WITH RAFM AND V-ALLOY FOR TBM AND DEMO Reviewed
T. Muroga, T. Tanaka, M. Kondo, T. Nagasaka, Q. Xu
FUSION SCIENCE AND TECHNOLOGY 56 ( 2 ) 897 - 901 2009.8
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HIGH PERFORMANCE CORROSION RESISTANCE OF NICKEL-BASED ALLOYS IN MOLTEN SALT FLIBE Reviewed
Masatoshi Kondo, Takuya Nagasaka, Takeo Muroga, Akio Sagara, Nobuaki Noda, Qi Xu, Daisuke Ninomiya, Nagura Masaru, Akihiro Suzuki, Takayuki Terai
FUSION SCIENCE AND TECHNOLOGY 56 ( 1 ) 190 - 194 2009.7
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Masatoshi Kondo, Takuya Nagasaka, Qi Xu, Takeo Muroga, Akio Sagara, Nobuaki Noda, Daisuke Ninomiya, Masaru Nagura, Akihiro Suzuki, Takayuki Terai, Naoki Fujii
FUSION ENGINEERING AND DESIGN 84 ( 7-11 ) 1081 - 1085 2009.6
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Takuya Nagasaka, Masatoshi Kondo, Takeo Muroga, Nobuaki Noda, Akio Sagara, Osamu Motojima, Akihiro Suzuki, Takayuki Terai
JOURNAL OF NUCLEAR MATERIALS 386-88 716 - 719 2009.4
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Metallurgical study on corrosion of austenitic steels in molten salt LiF-BeF2 (Flibe) Reviewed
Masatoshi Kondo, Takuya Nagasaka, Akio Sagara, Nobuaki Noda, Takeo Muroga, Qi Xu, Masaru Nagura, Akihiro Suzuki, Takayuki Terai
JOURNAL OF NUCLEAR MATERIALS 386-88 685 - 688 2009.4
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Design Integration of the LHD-type Energy Reactor FFHR2 towards Demo
Sagara, A., Imagawa, S., Kozaki, Y., Mitarai, O., Tanaka, T., Watanabe, T., Yanagi, N., Goto, T., Tamura, H., Takahata, K.
2009
-
Consideration of alumina coating fabricated by sol-gel method as MHD coating against PbLi
Ueki, Y., Kunugi, T., Kondo, M., Sagara, A., Morley, NB, Abdou, MA
2009
-
Design Integration of the LHD-type Energy Reactor FFHR2 towards Demo
Sagara, A., Imagawa, S., Kozaki, Y., Mitarai, O., Tanaka, T., Watanabe, T., Yanagi, N., Goto, T., Tamura, H., Takahata, K.
2009
-
Consideration of Alumina Coating Fabricated by Sol-gel Method as MHD Coating against PbLi
Ueki, Y., Kunugi, T., Kondo, M., Sagara, A., Morley, NB, Abdou, MA
2009
-
Consideration of Alumina Coating Fabricated by Sol-gel Method as MHD Coating against PbLi
Ueki, Y., Kunugi, T., Kondo, M., Sagara, A., Morley, NB, Abdou, MA
2009
-
Sc-doped CaZrO3 hydrogen sensor for liquid blanket system Reviewed
Masatoshi Kondo, Takeo Muroga, Koji Katahira, Tomoko Oshima
FUSION ENGINEERING AND DESIGN 83 ( 7-9 ) 1277 - 1281 2008.12
-
Qi Xu, Masatoshi Kondo, Takuya Nagasaka, Takeo Muroga, Masaru Nagura, Akihiro Suzuki
FUSION ENGINEERING AND DESIGN 83 ( 10-12 ) 1477 - 1483 2008.12
-
液体金属・溶融塩システムの水素モニターへの陽子導体の適用
Masatoshi KONDO
Journal of Power and Energy Systems (Web) 2008
-
Compatibility of reduced activation ferritic/martensitic steels with liquid breeders
Muroga, Takeo, Nagasaka, Takuya, Kondo, Masatoshi, Sagara, Akio, Noda, N., Suzuki, A., Terai, T.
Proceedings of 22nd IAEA Fusion Energy Conference 2008
-
Compatibility of reduced activation ferritic/martensitic steels with liquid breeders
Muroga, Takeo, Nagasaka, Takuya, Kondo, Masatoshi, Sagara, Akio, Noda, N., Suzuki, A., Terai, T.
Proceedings of 22nd IAEA Fusion Energy Conference 2008
-
Compatibility of reduced activation ferritic/martensitic steels with liquid breeders
Muroga, T., Nagasaka, T., Kondo, M., Sagara, A., Noda, N., Suzuki, A., Terai, T.
2008
-
Progress in flibe corrosion study toward material research loop and advanced liquid breeder blanket
Nagasaka, Takuya, Kondo, Masatoshi, Muroga, Takeo, Noda, N., Sagara, Akio, Motojima, Osamu, Suzuki, A., Terai, T.
IAEA FEC Proceedings 2008
-
Compatibility of Reduced Activation Ferritic/Martensitic Steels with Liquid Breeders
Nagasaka, T., Kondo, M., Sagara, A., Noda, N., Suzuki, A.
Research Report NIFS-Series 2008
-
液体金属・溶融塩システムの水素モニターへの陽子導体の適用
KONDO, Masatoshi, MUROGA, Takeo, KATAHIRA, Koji, OSHIMA, Tomoko
J Power Energy Syst (Web) 2 ( 2 ) 2008
-
Study of corrosion for development of fusion reactor liquid blanket (3). Evaluation of corrosion rate of steel products in liquid metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi
2008
-
Study of corrosion for development of fusion reactor liquid blanket (4). Improvement of corrosion resistance of steel products in molten salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Noda, Nobuaki, Muroga, Takeo, Ninomiya, Daisuke, Nagura, Masaru, Suzuki, Akihiro, Terai, Takayuki
2008
-
液体金属・溶融塩システムの水素モニターへの陽子導体の適用
KONDO, Masatoshi, MUROGA, Takeo, KATAHIRA, Koji, OSHIMA, Tomoko
J Power Energy Syst (Web) 2 ( 2 ) 2008
-
Study of corrosion for development of fusion reactor liquid blanket (4). Improvement of corrosion resistance of steel products in molten salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Noda, Nobuaki, Muroga, Takeo, Ninomiya, Daisuke, Nagura, Masaru, Suzuki, Akihiro, Terai, Takayuki
2008
-
Study of corrosion for development of fusion reactor liquid blanket (4). Improvement of corrosion resistance of steel products in molten salt
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio, Noda, Nobuaki, Muroga, Takeo, Ninomiya, Daisuke, Nagura, Masaru, Suzuki, Akihiro, Terai, Takayuki
2008
-
Study of corrosion for development of fusion reactor liquid blanket (3). Evaluation of corrosion rate of steel products in liquid metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi
2008
-
Progress in flibe corrosion study toward material research loop and advanced liquid breeder blanket
Nagasaka, T., Kondo, M., Muroga, T., Noda, N., Sagara, A., Motojima, O., Suzuki, A., Terai, T.
2008
-
Progress in flibe corrosion study toward material research loop and advanced liquid breeder blanket
Nagasaka, Takuya, Kondo, Masatoshi, Muroga, Takeo, Noda, N., Sagara, Akio, Motojima, Osamu, Suzuki, A., Terai, T.
IAEA FEC Proceedings 2008
-
Study of corrosion for development of fusion reactor liquid blanket (3). Evaluation of corrosion rate of steel products in liquid metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi
2008
-
Progress in Flibe Corrosion Study toward Material Research Loop and Advanced Liquid Breeder Blanket
Kondo, M., Muroga, T., Noda, N., Sagara, A., Motojima, O., Suzuki, A.
Research Report NIFS-Series 2008
-
Application of Proton Conductors to Hydrogen Monitoring for Liquid Metal and Molten Salt Systems
KONDO Masatoshi, MUROGA Takeo, KATAHIRA Koji, OSHIMA Tomoko
JPES 2 ( 2 ) 590 - 597 2008
-
Experimental study on corrosion of ceramic materials in natural convection lithium loop Reviewed
Masaru Nagura, Masatoshi Kondo, Akihiro Suzuki, Takeo Muroga, Takayuki Terai
FUSION SCIENCE AND TECHNOLOGY 52 ( 3 ) 630 - 634 2007.10
-
Fluoridation and oxidation behavior of JLF-1 and NIFS-HEAT-2 low activation structural materials
Nagasaka, T., Muroga, T., Kondo, M., Nishimura, H., Noda, N.
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(1). Corrosion characteristics of steel materials in molten salt Flibe
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(2). Corrosion characteristics of steel materials in liquid Li metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi, Kanemura, Takuji
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(1). Corrosion characteristics of steel materials in molten salt Flibe
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(1). Corrosion characteristics of steel materials in molten salt Flibe
Kondo, Masatoshi, Nagasaka, Takuya, Sagara, Akio
2007
-
Experimental Study on Corrosion of Steels in Flibe thermal convection loop
Kondo, M., Sagara, A., Nagasaka, T., Muroga, T., Nishimura, H., Suzuki, A., Noda, N., Nagura, M., Terai, T.
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(2). Corrosion characteristics of steel materials in liquid Li metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi, Kanemura, Takuji
2007
-
Corrosion study on development of liquid blanket system in fusion reactor.(2). Corrosion characteristics of steel materials in liquid Li metal
Kondo, Masatoshi, Muroga, Takeo, Nagasaka, Takuya, Xu, Qi, Kanemura, Takuji
2007
-
Metallurgical Study on Corrosion of Steels in Molten Flibe (LiF-BeF2) for Design of Flibe Corrosion Test Loop
Kondo, M., Nagasaka, T., Muroga, T., Sagara, A., Noda, N., Nagura, M., Suzuki, A., Terai, T.
Annual Report of National Institute for Fusion Science 454 - 454 2007
-
Fluoridation and oxidation behavior of JLF-1 and NIFS-HEAT-2 low activation structural materials
Nagasaka, T., Muroga, T., Kondo, M., Nishimura, H., Noda, N.
2007
-
Electrochemical approach to corrosion behavior of ferritic steels in Flibe melt
Nishimura, H., Suzuki, A., Terai, T., Kondo, M., Sagara, A., Noda, N.
2007
-
Experimental Study on Corrosion of Steels in Flibe thermal convection loop
Kondo, M., Sagara, A., Nagasaka, T., Muroga, T., Nishimura, H., Suzuki, A., Noda, N., Nagura, M., Terai, T.
2007
-
Fluoridation and oxidation behavior of JLF-1 and NIFS-HEAT-2 low activation structural materials
Kondo, M., Muroga, T., Noda, N., Sagara, A., Motojima, O., Suzuki, A.
Annual Report of National Institute for Fusion Science ( 2007 ) 453 - 453 2007
-
Study on control of oxygen concentration in lead-bismuth flow using lead oxide particles Reviewed
Masatoshi Kondo, Minoru Takahashi, Kuniaki Miura, Tatsuya Onizawa
JOURNAL OF NUCLEAR MATERIALS 357 ( 1-3 ) 97 - 104 2006.10
-
Corrosion resistance of Si- and Al-rich steels in flowing lead-bismuth Reviewed
Masatoshi Kondo, Minoru Takahashi
JOURNAL OF NUCLEAR MATERIALS 356 ( 1-3 ) 203 - 212 2006.9
-
Corrosion of steels with surface treatment and Al-alloying by GESA exposed in lead-bismuth Reviewed
A Heinzel, M Kondo, M Takahashi
JOURNAL OF NUCLEAR MATERIALS 350 ( 3 ) 264 - 270 2006.5
-
Study on metallurgical change of steels and ceramics in flowing lead-bismuth and chemical control of liquid alloy
Masatoshi KONDO
Study on metallurgical change of steels and ceramics in flowing lead-bismuth and chemical control of liquid alloy 2006.3
-
Corrosion of steels in lead-bismuth flow Reviewed
M Kondo, M Takahashi, N Sawada, K Hata
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43 ( 2 ) 107 - 116 2006.2
-
鉛‐ビスマス腐食試験施設で破断した管の冶金学的分析
KONDO, Masatoshi, TAKAHASHI, Minoru
J Nucl Sci Technol 43 ( 2 ) 2006
-
Corrosion Characteristics of Pre-Oxidized Steels in Pb-Bi Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 235 - 235 2006
-
Corrosion Characteristics of Pre-Oxidized Steels in Pb-Bi Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 235 - 235 2006
-
Corrosion Resistance of Si-and Al-Rich Steels in Flowing Lead Bismuth
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 219 - 219 2006
-
Study on Materials for Lead-Bismuth Cooled Fast Reactor
Takahashi, Minoru, Rivai, Abu Khalid, Dostal, Vaclav, Hata, Koji, Kondo, Masatoshi
Study on Materials for Lead-Bismuth Cooled Fast Reactor 2006
-
Performance of Solid Electrolyte Type Oxygen Sensor in Flowing Lead Bismuth
Kondo, Masatoshi, Takahashi, Minoru
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 241 - 241 2006
-
Corrosion Resistance of Si-and Al-Rich Steels in Flowing Lead Bismuth
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 219 - 219 2006
-
Corrosion Resistance of Si-and Al-Rich Steels in Flowing Lead Bismuth
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 219 - 219 2006
-
Corrosion Characteristics of Pre-Oxidized Steels in Pb-Bi Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 30 ( 1/2 ) 235 - 235 2006
-
Study on Materials for Lead-Bismuth Cooled Fast Reactor
Takahashi, Minoru, Rivai, Abu Khalid, Dostal, Vaclav, Hata, Koji, Kondo, Masatoshi
Study on Materials for Lead-Bismuth Cooled Fast Reactor 2006
-
Study on Materials for Lead-Bismuth Cooled Fast Reactor
Takahashi, Minoru, Rivai, Abu Khalid, Dostal, Vaclav, Hata, Koji, Kondo, Masatoshi
Study on Materials for Lead-Bismuth Cooled Fast Reactor 2006
-
鉛‐ビスマス流動場における鋼材の腐食
KONDO, Masatoshi, TAKAHASHI, Minoru, SAWADA, Naoki, HATA, Koji
J Nucl Sci Technol 43 ( 2 ) 2006
-
鉛‐ビスマス流動場における鋼材の腐食
KONDO, Masatoshi, TAKAHASHI, Minoru, SAWADA, Naoki, HATA, Koji
J Nucl Sci Technol 43 ( 2 ) 2006
-
鉛‐ビスマス腐食試験施設で破断した管の冶金学的分析
KONDO, Masatoshi, TAKAHASHI, Minoru
J Nucl Sci Technol 43 ( 2 ) 2006
-
Metallurgical analysis of a tube ruptured in the lead bismuth corrosion test facility Reviewed
Masatoshi Kondo, Minoru Takahashi
Journal of Nuclear Science and Technology 43 ( 2 ) 174 - 178 2006
-
近藤正聡
核データニュース ( 82 ) 2005.10
-
Metallurgical study on erosion and corrosion behaviors of steels exposed to liquid lead-bismuth flow Reviewed
M Kondo, M Takahashi, T Suzuki, K Ishikawa, K Hata, SZ Qiu, H Sekimoto
JOURNAL OF NUCLEAR MATERIALS 343 ( 1-3 ) 349 - 359 2005.8
-
Metallurgical Study on Electro-Magnetic Flow Meter and Pump for Liquid Lead-Bismuth Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 71 - 71 2005
-
Control of Oxygen Concentration in Lead Bismuth Flow
Takahashi, M., Kondo, M.
7th International Workshop on Spallation Materials Technology, IWSMT-7, Thun, Switzerland 2005
-
Corrosion resistance of high Cr steels and ceramic materials in lead-bismuth flow
Takahashi, Minoru, Kondo, Masatoshi
2005
-
Control of Oxygen Concentration in Lead Bismuth Flow
Takahashi, M., Kondo, M.
7th International Workshop on Spallation Materials Technology, IWSMT-7, Thun, Switzerland 2005
-
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth
Hirabayashi, M., Kondo, M., Ara, K., Takahashi, M.
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth ( ICONE13-50001 ) 2005
-
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth
Hirabayashi, M., Kondo, M., Ara, K., Takahashi, M.
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth ( ICONE13-50001 ) 2005
-
Corrosion resistance of high Cr steels and ceramic materials in lead-bismuth flow
Takahashi, Minoru, Kondo, Masatoshi
2005
-
Experimental Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 76 - 76 2005
-
Development of ultrasonic flow meter for liquid lead-bismuth flow
Hirabayashi, Masaru, Ara, K., Kondo, M., Takahashi, Minoru
The 13th international conference on nuclear engineering abstracts 2005
-
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth
Hirabayashi, M., Kondo, M., Ara, K., Takahashi, M.
Development of Ultrasonic Flow Meter for Liquid Lead-Bismuth ( ICONE13-50001 ) 2005
-
Experimental Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 76 - 76 2005
-
Metallurgical Study on Electro-Magnetic Flow Meter and Pump for Liquid Lead-Bismuth Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 71 - 71 2005
-
Metallurgical Study on Electro-Magnetic Flow Meter and Pump for Liquid Lead-Bismuth Flow
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 71 - 71 2005
-
Experimental Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi
Takahashi, M., Kondo, M.
BULLETIN-RESEARCH LABORATORY FOR NUCLEAR REACTORS 29 ( 1/2 ) 76 - 76 2005
-
Development of ultrasonic flow meter for liquid lead-bismuth flow
Hirabayashi, Masaru, Ara, K., Kondo, M., Takahashi, Minoru
The 13th international conference on nuclear engineering abstracts 2005
-
ルミネッセンス (発光) で探る古代情報, 僕達が今からできる原子力国際交流への準備―原子力英語の訓練―Nuclear English
Masatoshi KONDO
日本原子力学会誌 2005
-
Metallurgical study on electro-magnetic flow meter and pump for liquid lead-bismuth flow Reviewed
M Kondo, M Takahashi
PROGRESS IN NUCLEAR ENERGY 47 ( 1-4 ) 639 - 647 2005
-
Control of oxygen concentration in lead-bismuth flow by temperature control of solid lead oxide
Masatoshi Kondo, Minoru Takahashi
Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 2 958 - 964 2005
-
Corrosion characteristics of pre-oxidized steels in Pb-Bi flow
Masatoshi Kondo, Minoru Takahashi
Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05 2 939 - 946 2005
-
Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi
Kondo, M., Takahashi, M.
12th International Conference on Nuclear Engineering (ICONE12) 400 2004
-
Effect of surface roughness and pre-oxidation of steels on corrosion behavior in a liquid lead-bismuth flow
Kondo, M., Takahashi, M.
2004 ANS Annual Meeting, 2004 International Congress on Advances in Nuclear Power Plants (ICAPP'04), Pittsburgh, PA USA, June 13-17 2004
-
Atoms for Peace50 周年によせて
Masatoshi KONDO
日本原子力学会誌 2004
-
Metallurgical Study and Performance of Electro-magnetic Flow Meter for a Liquid Lead-bismuth Flow
Kondo, M., Takahashi, M.
12th International Conference on Nuclear Engineering (ICONE12) 400 2004
-
Effect of Surface Roughness of Steels on Oxide Layer Formation in a Liquid Lead-Bismuth Flow
Kondo, Masatoshi, Takahashi, Minoru, YOSHIDA, Susumu, SAWADA, Naoki
2004
-
Metallurgical study on performance of electro-magnetic flow meter for liquid lead bismuth
KONDO, Masatoshi, Takahashi, Minoru
Proceedings of ICONE12 (CD-ROM) 400 2004
-
Metallurgical study on performance of electro-magnetic flow meter for liquid lead bismuth
KONDO, Masatoshi, Takahashi, Minoru
Proceedings of ICONE12 (CD-ROM) 400 2004
-
Effect of surface roughness and pre-oxidation of steels on corrosion behavior in a liquid lead-bismuth flow
Kondo, M., Takahashi, M.
2004 ANS Annual Meeting, 2004 International Congress on Advances in Nuclear Power Plants (ICAPP'04), Pittsburgh, PA USA, June 13-17 2004
-
Metallurgical study on performance of electro-magnetic flow meter for liquid lead bismuth
KONDO, Masatoshi, Takahashi, Minoru
Proceedings of ICONE12 (CD-ROM) 400 2004
-
Metallurgical Study and Performance of Electro-magnetic Flow Meter for a Liquid Lead-bismuth Flow
Kondo, M., Takahashi, M.
12th International Conference on Nuclear Engineering (ICONE12) 400 2004
-
Effect of Surface Roughness of Steels on Oxide Layer Formation in a Liquid Lead-Bismuth Flow
Kondo, Masatoshi, Takahashi, Minoru, YOSHIDA, Susumu, SAWADA, Naoki
2004
-
Studies on Pb-Bi Flow Technology and Steel Compatibility with Pb-Bi
Kondo, M., Takahashi, M.
12th International Conference on Nuclear Engineering (ICONE12) 400 2004
-
Experimental study on erosion/corrosion behavior of stainless steel in a liquid lead bismuth flow
KONDO, Masatoshi, Takahashi, Minoru
6th International Workshop on Spallation Materials Technology (IWSMT6), November 30-December 5, Hayama 2003
-
Experimental study on erosion/corrosion behavior of stainless steel in a liquid lead bismuth flow
KONDO, Masatoshi, Takahashi, Minoru
6th International Workshop on Spallation Materials Technology (IWSMT6), November 30-December 5, Hayama 2003
-
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow
KONDO, MASATOSHI, TAKAHASHI, MINORU
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow 2003
-
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow
KONDO, MASATOSHI, TAKAHASHI, MINORU
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow 2003
-
Corrosion of Steels in Lead-Bismuth Flow
Kondo, Masatoshi, Takahashi, Minoru, Sawada, Naoki, HATA, Koji
Zairyo-to-Kankyo 53 159 - 159 2003
-
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow
KONDO, MASATOSHI, TAKAHASHI, MINORU
Metallurgical study of erosion and corrosion behavior in stainless steels exposed to a liquid lead-bismuth flow 2003
-
Experimental Study on Steel Corrosion in a Pb-Bi Flow
Takahashi, Minoru, Kondo, Masatoshi, Hata, Kouji, Yoshida, Susumu, Sawada, Naoki
Russian Forum for Science and Technology Fast Neutron Reactors, Conference:«Heavy Liquid Metal Coolants in Nuclear Technologies (HLMC-2003), December 8-12, Obninsk 2003
-
Experimental Study on Steel Corrosion in a Pb-Bi Flow
Takahashi, Minoru, Kondo, Masatoshi, Hata, Kouji, Yoshida, Susumu, Sawada, Naoki
Russian Forum for Science and Technology Fast Neutron Reactors, Conference:«Heavy Liquid Metal Coolants in Nuclear Technologies (HLMC-2003), December 8-12, Obninsk 2003
-
Design of material strength test in lead-bismuth flow Reviewed
Masatoshi Kondo, Koji Hata, Minoru Takahashi
International Conference on Nuclear Engineering, Proceedings, ICONE 4 959 - 962 2002
-
プラズマ・核融合学会誌= Journal of plasma and fusion research 78 (7), 668-677, 2002-07-25
Masatoshi KONDO
Progress of theoretical physics. Supplement 2001
-
液体だけど水じゃない-次世代ブランケット・ダイバータ研究開発の現状と課題
Masatoshi KONDO
J. Nucl. Mater 1995
-
プラズマ・核融合学会誌= Journal of plasma and fusion research 79 (12), 1216-1217, 2003-12-25
Masatoshi KONDO
J. Nucl. Mater 1989
MISC
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Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts (5) Excellent corrosion resistance of FeCrAlZr-ODS alloy in high-temperature liquid lead lithium
畑山奨, 大野直子, 坂本寛, 近藤正聡
日本原子力学会春の年会予稿集(CD-ROM) 2021 2021
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Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts (1) Study on application of Al-contained steels in advanced liquid blanket systems
田中照也, 近藤正聡, 大野直子, 笠田竜太, 横峯健彦, 浜地志憲, 秋吉優史
日本原子力学会春の年会予稿集(CD-ROM) 2021 2021
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Chemical compatibility of ODS FeCrAl alloys for liquid Sn divertor concepts
宮川幸大, 近藤正聡, 大野直子, 笠田竜太, HAO Yu, 坂本寛, 田中照也
日本原子力学会秋の大会予稿集(CD-ROM) 2021 2021
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Application of FeCrAlZr-ODS alloy for advanced liquid blanket and divertor concepts (4) Experimental study on chemical compatibility for the development of fusion reactor components
近藤正聡, 宮澤順一, 田中照也, 大野直子, 秋吉優史, 坂本寛, 植木祥高, 菱沼良光, 笠田竜太, 波多野雄治, PINT Bruce, JIHEON Jun, RUSSEL Nick
日本原子力学会春の年会予稿集(CD-ROM) 2021 2021
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Chemical compatibility of liquid tin (Sn) (1) Corrosion characteristics of steels
近藤正聡, 秋吉優史, 大野直子, 田中照也
日本原子力学会春の年会予稿集(CD-ROM) 2020 2020
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ベトナム研修生向け原子力工学基礎教育(1)カリキュラムと教育実績
KAMEYAMA TAKANORI, ITO ATSUSHI, YOSHIDA SHIGEO, KANI YOSHIO, ASANUMA NORIKO, KONDO MASATOSHI, TAHARA YOSHIHISA
日本原子力学会春の年会予稿集(CD-ROM) 2015 ROMBUNNO.D17 2015.3
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液体増殖材用リチウム合金の合成手法に関する研究(2)リチウム濃度の調整
KONDO MASATOSHI, NAKAJIMA YU
日本原子力学会春の年会予稿集(CD-ROM) 2014 ROMBUNNO.E41 2014.3
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液体金属場における材料酸化挙動の電気化学インピーダンス解析
SUZUKI NARUMI, KONDO MASATOSHI, MUROGA TAKEO, TANAKA TERUYA
日本原子力学会春の年会予稿集(CD-ROM) 2014 ROMBUNNO.E40 2014.3
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核融合炉用液体リチウム合金燃料増殖材の合成・濃度調整手法に関する研究
NAKAJIMA YU, KONDO MASATOSHI
核融合エネルギー連合講演会予稿集 10th (CD-ROM) ROMBUNNO.20-098 2014
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静止場腐食試験による液体増殖材及び液体金属とブランケット構造材料との共存性評価
KONDO MASATOSHI, ISHII MASAOMI, MUROGA TAKEO
核融合エネルギー連合講演会予稿集 10th (CD-ROM) ROMBUNNO.20-101 2014
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電気化学インピーダンス法による液体金属鉛リチウム場の腐食挙動解析
KONDO MASATOSHI, SUZUKI NARUMI, NAKAJIMA YU, TANAKA TERUYA, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2013 ROMBUNNO.B34 2013.8
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慣性核融合炉液体ブランケットにおける液体増殖材の放射化評価
NAKAJIMA YU, KONDO MASATOSHI, NORIMATSU TAKAYOSHI
日本原子力学会秋の大会予稿集(CD-ROM) 2013 ROMBUNNO.B07 2013.8
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鉛リチウム自然対流ループとヒートパルス流速測定法に関する研究
KONDO MASATOSHI, SHIBANO KYOHEI, MUROGA TAKEO, TANAKA TERUYA
日本原子力学会春の年会予稿集(CD-ROM) 2013 ROMBUNNO.K27 2013.3
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液体増殖材用リチウム合金の合成手法に関する研究
NAKAJIMA YU, KONDO MASATOSHI
日本原子力学会春の年会予稿集(CD-ROM) 2013 ROMBUNNO.K26 2013.3
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環境放射能に関する原子力人材育成(1)除染実習の概要
KOZAKI TAMOTSU, FUJIYOSHI RYOKO, OTA TOMOKO, WATANABE NAOKO, NAMBA KENJI, SHIBASAKI NAOAKI, NAGAHASHI YOSHITAKA, NAGAOKA TOORU, SUZUKI YOSHINORI, KONDO MASATOSHI, TAGAMI KEIKO, ONUKI TOSHIHIKO, KOZAI NAOFUMI
日本原子力学会春の年会予稿集(CD-ROM) 2013 ROMBUNNO.E23 2013.3
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Study on Pb-17Li natural convection loop and heat pulse flow meter
Kondo Masatoshi, Shibano kyouhei, Tanaka Teruya, Muroga Takeo
Proceedings of AESJ 2013 ( 0 ) 575 - 575 2013
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Study on fabrication and properties of lithium alloys with various Li concentration as fusion liquid breeders
Nakajima Yuu, Kondo Masatoshi
Proceedings of AESJ 2013 ( 0 ) 574 - 574 2013
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Capacity building on environmental radioactivity:(1) Outline of environmental remediation
Kozaki Tamotsu, Fujiyoshi Ryoko, Ohta Tomoko, Watanabe Naoko, Nanba Kenji, Shibasaki Naoaki, Nagahashi Yoshitaka, Nagaoka Toru, Suzuki Yoshinori, Kondo Masatoshi, Tagami Keiko, Ohnuki Toshihiko, Kozai Naofumi
Proceedings of AESJ 2013 ( 0 ) 2013
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核融合炉ブランケット液体増殖材の沸点評価に関する研究
NAKAJIMA YU, KONDO MASATOSHI
日本原子力学会秋の大会予稿集(CD-ROM) 2012 ROMBUNNO.E06 - 667 2012.9
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液体金属鉛リチウム静止場における低放射化フェライト鋼の腐食特性に関する研究
KONDO MASATOSHI, MOCHIHARA RYO, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2012 ROMBUNNO.E08 - 669 2012.9
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核融合炉液体ブランケットの液体金属流動場におけるヒートパルス流速測定法に関する研究
SHIBANO KYOHEI, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2012 ROMBUNNO.E07 - 668 2012.9
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水素・熱分離回収実験溶融塩ループOrosh2i‐1における流動実験(1)―流動ループ試験―
TANAKA TERUYA, SAGARA AKIO, HISHINUMA YOSHIMITSU, GOTO TAKUYA, NAGASAKA TAKUYA, MUROGA TAKEO, KONDO MASATOSHI, WATANABE TAKASHI, FUKADA SATOSHI
日本原子力学会春の年会予稿集(CD-ROM) 2012 ROMBUNNO.A22 2012.3
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原子力工学教育における原子炉模型論
近藤 正聡, 鈴木 成美
研究資料集 20 21 - 31 2012
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Study on heat-pulse flowmeter on liquid metal flow in fusion reactor
Shibano Kyohei, Kondo Masatoshi, Muroga Takeo
Proceedings of AESJ 2012 ( 0 ) 668 - 668 2012
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Study on boiling point of liquid breeders for fusion reactor blanket
Nakazima Yuu, Kondo Masatoshi
Proceedings of AESJ 2012 ( 0 ) 667 - 667 2012
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Study on corrosion of reduced activation ferritic martensitic steel in static Pb-17Li
Kondo Masatoshi, Mochihara Ryo, Muroga Takeo
Proceedings of AESJ 2012 ( 0 ) 669 - 669 2012
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Recovery of Lithium from Seawater
YOSHIZUKA Kazuharu, KONDO Masatoshi
Journal of plasma and fusion research 87 ( 12 ) 795 - 800 2011.12
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海水からのリチウム回収
YOSHIZUKA KAZUHARU, KONDO MASATOSHI
プラズマ・核融合学会誌 87 ( 12 ) 795 - 800 2011.12
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水素・熱回収両立試験溶融塩ループOrosh2i‐1における水素回収部の水素透過能
NAGASAKA TAKUYA, TANAKA TERUYA, SAGARA AKIO, MUROGA TAKEO, KONDO MASATOSHI, WATANABE TAKASHI, FUKADA SATOSHI, YUKAWA HIROSHI, NAMBU TOMONORI, IIKUBO TOMOHITO
日本原子力学会秋の大会予稿集(CD-ROM) 2011 ROMBUNNO.G22 2011.9
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核融合炉ブランケットシステムのための弗化物系溶融塩中の構造材料表面の窒化処理
WATANABE TAKASHI, KONDO MASATOSHI, SAGARA AKIO
日本原子力学会春の年会予稿集(CD-ROM) 2011 ROMBUNNO.O24 2011.3
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水素・熱回収両立試験溶融塩ループOrosh2i‐1におけるFlinakからの水素放出特性の評価
TANAKA TERUYA, KONDO MASATOSHI, MUROGA TAKEO, SAGARA AKIO, OSHIMA TOMOKO
日本原子力学会春の年会予稿集(CD-ROM) 2011 ROMBUNNO.P40 2011.3
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水素・熱回収両立試験溶融塩ループOrosh2i‐1における水素回収部の設計と製作
NAGASAKA TAKUYA, TANAKA TERUYA, KONDO MASATOSHI, SAGARA AKIO, MUROGA TAKEO, WATANABE TAKASHI, FUKADA SATOSHI, YUKAWA HIROSHI, NAMBU TOMONORI, IIKUBO TOMOHITO
日本原子力学会春の年会予稿集(CD-ROM) 2011 ROMBUNNO.P39 2011.3
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液体増殖ブランケット用固体電解質水素センサを用いた液体増殖材の水素溶解挙動の研究
OSHIMA TOMOKO, KONDO MASATOSHI, TANAKA MASAHIRO, MUROGA TAKEO, SAGARA AKIO
日本原子力学会春の年会予稿集(CD-ROM) 2011 ROMBUNNO.P37 2011.3
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4.3 Effort on Lithium Compatibility Study toward Happy Ending(4. Forefront of Compatibility Study,<Special Topic Article>Compatibility of Materials in Fusion Blanket Systems)
KONDO Masatoshi, TSISAR Valentyn, TERAI Takayuki, SUZUKI Akihiro
Journal of plasma and fusion research 86 ( 7 ) 408 - 412 2010.7
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核融合炉ブランケット燃料増殖材・冷却材中の材料の共存性 4.共存性研究の最前線 4.4 液体金属鉛リチウム中の共存性について(構造材料と機能性材料) 4.4.1 液体金属鉛リチウム中の低放射化フェライト鋼の共存性
TAKAHASHI MINORU, KONDO MASATOSHI
プラズマ・核融合学会誌 86 ( 7 ) 413 - 416 2010.7
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核融合炉ブランケット燃料増殖材・冷却材中の材料の共存性 3 核融合炉ブランケットの共存性の評価手法
KONDO MASATOSHI, TSISAR VALENTYN, HIROSE TAKANORI, SEKI YOJI
プラズマ・核融合学会誌 86 ( 7 ) 393 - 397 2010.7
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核融合炉ブランケット燃料増殖材・冷却材中の材料の共存性 4 共存性研究の最前線 4.3 純粋なリチウムに恋する候補構造材料の物語
KONDO MASATOSHI, TSISAR VALENTYN, TERAI TAKAYUKI, SUZUKI AKIHIRO
プラズマ・核融合学会誌 86 ( 7 ) 408 - 412 2010.7
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4.2 Oxidation in Molten Fluoride Salt(4. Forefront of Compatibility Study,<Special Topic Article>Compatibility of Materials in Fusion Blanket Systems)
KONDO Masatoshi, SUZUKI Akihiro, NAGASAKA Takuya, TERAI Takayuki, SAGARA Akio
Journal of plasma and fusion research 86 ( 7 ) 402 - 407 2010.7
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3. Technology for Compatibility Study for Fusion Blanket System(<Special Topic Article>Compatibility of Materials in Fusion Blanket Systems)
KONDO Masatoshi, TSISAR Valentyn, HIROSE Takanori, SEKI Yohji
Journal of plasma and fusion research 86 ( 7 ) 393 - 397 2010.7
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4.4.1 Compatibility of Reduced Activation Ferritic/Martensitic Steel in Pb-17Li(4.4 Compatibility of Materials with Liquid Metal Pb-17Li,4. Forefront of Compatibility Study,<Special Topic Article>Compatibility of Materials in Fusion Blanket Systems)
TAKAHASHI Minoru, KONDO Masatoshi
Journal of plasma and fusion research 86 ( 7 ) 413 - 416 2010.7
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核融合炉ブランケット燃料増殖材・冷却材中の材料の共存性 4 共存性研究の最前線 4.2 フッ化物系溶融塩の中の酸化反応―溶融塩ブランケットの共存性―
KONDO MASATOSHI, SUZUKI AKIHIRO, NAGASAKA TAKUYA, TERAI TAKAYUKI, SAGARA AKIO
プラズマ・核融合学会誌 86 ( 7 ) 402 - 407 2010.7
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トリチウム透過防止セラミックス被覆材料の腐食特性と伝熱特性
WATANABE TAKASHI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
日本原子力学会春の年会予稿集(CD-ROM) 2010 ROMBUNNO.M19 2010.3
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水素・熱分離回収実験溶融塩ループOrosh2i‐1における水素回収部の検討
NAGASAKA TAKUYA, KONDO MASATOSHI, SAGARA AKIO, MUROGA TAKEO, WATANABE TAKASHI, FUKADA SATOSHI, IIKUBO TOMOHITO
日本原子力学会春の年会予稿集(CD-ROM) 2010 ROMBUNNO.M03 2010.3
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水素・熱分離回収実験溶融塩ループOrosh2i‐1の製作と研究計画
SAGARA AKIO, NAGASAKA TAKUYA, KONDO MASATOSHI, TANAKA TERUYA, MUROGA TAKEO, WATANABE TAKASHI, FUKADA SATOSHI
日本原子力学会春の年会予稿集(CD-ROM) 2010 ROMBUNNO.M24 2010.3
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液体ブランケットの熱・水素回収制御のための界面熱伝達機構の研究
WATANABE TAKASHI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
核融合エネルギー連合講演会予稿集 8th (CD-ROM) ROMBUNNO.10A-74P 2010
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液体増殖ブランケット用固体電解質水素センサを用いた溶融塩Flinakの水素溶解挙動の研究
OSHIMA TOMOKO, KONDO MASATOSHI, TANAKA MASAHIRO, MUROGA TAKEO, SAGARA AKIO
核融合エネルギー連合講演会予稿集 8th (CD-ROM) ROMBUNNO.10A-73P 2010
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液体増殖ブランケット用Pd電極型固体電解質水素センサを用いた溶融塩Flinakの水素溶解挙動の研究
大島智子, 大島智子, 近藤正聡, 近藤正聡, 田中将裕, 室賀健夫, 室賀健夫, 相良明男, 相良明男
プラズマ・核融合学会年会(Web) 27th 2010
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液体LiPb中におけるJLF‐1の腐食特性に関する研究
ZHOU XINGHUA, TAKAHASHI MINORU, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2009 P19 2009.8
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核融合炉燃料システムにおけるトリチウム透過量評価と透過防止技術の新展開(5)溶融塩からの水素・熱回収両立試験及び高温水素透過材料の腐食挙動
NAGASAKA TAKUYA, SAGARA AKIO, KONDO MASATOSHI, MUROGA TAKEO, HISHINUMA YOSHIMITSU, TANAKA TERUYA, LI YANFEN, OSHIMA TOMOKO, ZHANG DONGXUN, WATANABE TAKASHI, FUKADA SATOSHI
日本原子力学会秋の大会予稿集(CD-ROM) 2009 P37 2009.8
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核融合炉燃料システムにおけるトリチウム透過量評価と透過防止技術の新展開―(6)水素・熱回収システムにおける水素透過抑制のための被覆開発―
TANAKA TERUYA, HISHINUMA YOSHIMITSU, MUROGA TAKEO, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, ZHANG DONXUN, WATANABE TAKASHI, SUZUKI AKIHIRO
日本原子力学会秋の大会予稿集(CD-ROM) 2009 P38 2009.8
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トリチウム増殖材Flibeからの不純物金属電析効率向上に係るアノード・カソードの検討
OYAMA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
日本原子力学会秋の大会予稿集(CD-ROM) 2009 P20 2009.8
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PbLi MHD熱流動研究に向けたゾルゲル法アルミナ被膜の適用可能性の検討
UEKI YOSHITAKA, KUNUGI TOMOAKI, KONDO MASATOSHI, SAGARA AKIO, MORLEY NEIL B, ABDOU MOHAMED A
日本原子力学会秋の大会予稿集(CD-ROM) 2009 ( 0 ) P18 - 758 2009.8
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溶融塩Flibe及びFlinak中の不純物制御に関する研究
KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, MUROGA TAKEO, NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, FUJII NAOKI
日本原子力学会春の年会予稿集(CD-ROM) 2009 M28 2009.3
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電気化学測定を用いた核融合炉溶融塩増殖材Flibe中での腐食挙動研究(3)構造材料のFlibe中電気化学特性評価
NINOMIYA DAISUKE, OYAMA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
日本原子力学会春の年会予稿集(CD-ROM) 2009 M26 2009.3
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パラジウム膜状電極を用いた液体ブランケット用水素センサの研究
OSHIMA TOMOKO, KONDO MASATOSHI, TANAKA MASAHIRO, MUROGA TAKEO
日本原子力学会春の年会予稿集(CD-ROM) 2009 M29 2009.3
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電析を用いたトリチウム増殖材Flibeからの不純物除去
OYAMA DAISUKE, NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
日本原子力学会春の年会予稿集(CD-ROM) 2009 M27 2009.3
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液体ブランケット用固体電解質水素(同位体)センサーの電極高度化研究
OSHIMA TOMOKO, KONDO MASATOSHI, TANAKA MASAHIRO, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2008 G08 2008.8
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Flibe中及びフッ化水素ガス中における低放射化材料のフッ化・酸化挙動
NAGASAKA TAKUYA, KONDO MASATOSHI, MUROGA TAKEO, NODA NOBUAKI, SAGARA AKIO, MOTOJIMA OSAMU, SUZUKI AKIHIRO, TERAI TAKAYUKI
日本原子力学会秋の大会予稿集(CD-ROM) 2008 G31 2008.8
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電気化学測定を用いた核融合炉溶融塩増殖材Flibe中での腐食挙動研究(2)参照電極の試作
NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO
日本原子力学会秋の大会予稿集(CD-ROM) 2008 G33 2008.8
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溶融塩Flibe及びFlinak中のHF濃度滴定と鋼材の腐食特性に関する研究
KONDO MASATOSHI, NAGASAKA TAKUYA, MUROGA TAKEO, SAGARA AKIO, FUJII NAOKI, NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI
日本原子力学会秋の大会予稿集(CD-ROM) 2008 G32 2008.8
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溶融塩Flibe中での腐食研究のための電気化学測定用参照電極の試作
NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, SAGARA AKIO
核融合エネルギー連合講演会予稿集 7th 87 2008.5
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低放射化フェライト鋼及びバナジウム合金の酸化,フッ化挙動
NAGASAKA TAKUYA, KONDO MASATOSHI, MUROGA TAKEO, NODA NOBUAKI, SAGARA AKIO, MOTOJIMA OSAMU, SUZUKI AKIHIRO, TERAI TAKAYUKI
核融合エネルギー連合講演会予稿集 7th 124 2008.5
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溶融塩中の鋼材の腐食特性に関する研究
KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, NODA NOBUAKI, MUROGA TAKEO, NAGURA MASARU, NINOMIYA DAISUKE, SUZUKI AKIHIRO, TERAI TAKAYUKI
核融合エネルギー連合講演会予稿集 7th 119 2008.5
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核融合炉液体ブランケット開発における腐食研究(3)液体金属中における鋼材の腐食率評価に関する検討
KONDO MASATOSHI, QI XU, MUROGA TAKEO, NAGASAKA TAKUYA
材料と環境講演集 2008 205 - 208 2008.4
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核融合炉液体ブランケット開発における腐食研究(4)溶融塩中における鋼材の耐食性向上に関する検討
KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, NODA NOBUAKI, MUROGA TAKEO, NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI
材料と環境講演集 2008 209 - 212 2008.4
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酸化エルビウムのリチウム中腐食生成物(2)
NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会春の年会予稿集(CD-ROM) 2008 F19 2008.3
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溶融塩Flibe中における鋼材の腐食特性
KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, NODA NOBUAKI, MUROGA TAKEO, QI XU, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI
日本原子力学会春の年会予稿集(CD-ROM) 2008 F13 2008.3
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液体ブランケット用水素センサーに関する研究(3)
OSHIMA TOMOKO, KONDO MASATOSHI, MUROGA TAKEO, KATAHIRA KOJI
日本原子力学会春の年会予稿集(CD-ROM) 2008 F15 2008.3
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電気化学測定を用いた核融合炉溶融塩増殖材Flibe中での腐食挙動研究(1)溶融塩純化と電極材料選定
NINOMIYA DAISUKE, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, NODA NOBUAKI
日本原子力学会春の年会予稿集(CD-ROM) 2008 F12 2008.3
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液体ブランケット用水素センサーの電極高度化研究
大島智子, 大島智子, 近藤正聡, 近藤正聡, 田中将裕, 室賀健夫, 室賀健夫
プラズマ・核融合学会年会(Web) 25th 2008
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核融合炉液体ブランケット開発における腐食研究(1)溶融塩Flibe中における鋼材の腐食特性
KONDO MASATOSHI, NAGASAKA TAKUYA, SAGARA AKIO, NODA NOBUAKI, MUROGA TAKEO, NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, WATANABE TOSHITOMO, QI XU
材料と環境討論会講演集 54th 165 - 168 2007.10
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核融合炉液体ブランケットシステム開発における腐食研究(2)液体金属Li中における鋼材の腐食特性
KONDO MASATOSHI, QI XU, MUROGA TAKEO, NAGASAKA TAKUYA, KANEMURA TAKUJI
材料と環境討論会講演集 54th 169 - 172 2007.10
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酸化エルビウムのリチウム中腐食生成物
NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2007 L13 2007.9
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液体ブランケット用水素センサーに関する研究(2)
KONDO MASATOSHI, MUROGA TAKEO, KATAHIRA KOJI, OSHIMA TOMOKO
日本原子力学会秋の大会予稿集(CD-ROM) 2007 L43 2007.9
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高温融体用メカニカルリフトポンプの研究開発
MATSUSHITA IZURU, YAMAGUCHI MASATOSHI, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会秋の大会予稿集(CD-ROM) 2007 L45 2007.9
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ICONE15-10588 APPLICATION OF PROTON CONDUCTORS TO HYDROGEN MONITORING FOR LIQUID METAL AND MOLTEN SALT SYSTEMS
Kondo Masatoshi, Muroga Takeo, Katahira Koji, Oshima Tomoko
Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2007 ( 15 ) "ICONE1510588 - 1"-"ICONE1510588-8" 2007.4
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低放射化フェライト鋼JLF‐1と高純度Flibeとの共存性
NAGASAKA TAKUYA, KONDO MASATOSHI, NODA NOBUAKI, MUROGA TAKEO, SAGARA AKIO, NISHIMURA HIDETOSHI, SUZUKI AKIHIRO, TERAI TAKAYUKI
日本原子力学会春の年会要旨集(CD-ROM) 2007 M13 2007.3
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液体ブランケット用水素センサーに関する研究
KONDO MASATOSHI, MUROGA TAKEO, KATAHIRA KOJI, OSHIMA TOMOKO
日本原子力学会春の年会要旨集(CD-ROM) 2007 M44 2007.3
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酸化エルビウムの自然対流リチウムループ中での腐食挙動
NAGURA MASARU, SUZUKI AKIHIRO, TERAI TAKAYUKI, KONDO MASATOSHI, MUROGA TAKEO
日本原子力学会春の年会要旨集(CD-ROM) 2007 M39 2007.3
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30pB24P Study on Proton Conducting Ceramic Sensor for Hydrogen Measurement in Liquid Blanket System
近藤 正聡, 室賀 健夫, 片平 幸司, 大島 智子
プラズマ・核融合学会年会予稿集 ( 23 ) 210 - 210 2006.11
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Metallurgical analysis of a tube ruptured in the lead bismuth corrosion test facility
M Kondo, M Takahashi
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43 ( 2 ) 174 - 178 2006.2
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Corrosion of steels in lead-bismuth flow
M Kondo, M Takahashi, N Sawada, K Hata
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 43 ( 2 ) 107 - 116 2006.2
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学生とシニアの対話;社会の矛盾を双方で考え,学生のキャリアデザイン支援,夢支援
TAKEUCHI TETSUO, HAYASHI TSUTOMU, HIROYA YOSHINORI, KONDO MASASATO, NISHIYAMA JUN, YOSHIDA NAOHIRO, MIKI YOSUKE, ITO NAOKO, AMANO OSAMU
日本原子力学会春の年会要旨集 43rd SO1-SO5 2005.3
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Pb‐Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 III‐(3)超音波流量計センサー接液部の腐食特性‐
KONDO MASATOSHI, TAKAHASHI MINORU, ARA KUNIAKI, HIRABAYASHI MASARU
日本原子力学会春の年会要旨集 43rd 348 2005.3
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Pb‐Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 III‐(1)粒状酸化鉛直接浸漬による酸素濃度制御方法の開発‐
TAKAHASHI MINORU, KONDO MASATOSHI
日本原子力学会春の年会要旨集 43rd 346 2005.3
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Pb‐Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 III‐(2)鉛ビスマス超音波流量計測に関する研究‐
ARA KUNIAKI, HIRABAYASHI MASARU, NAGAI KEIICHI, KONDO MASATOSHI, TAKAHASHI MINORU
日本原子力学会春の年会要旨集 43rd 347 2005.3
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2004年秋の大会 : 学生連絡会企画第8回ポスターセッション
近藤 正聡
日本原子力学会誌 = Journal of the Atomic Energy Society of Japan 46 ( 12 ) 853 - 853 2004.12
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Pb‐Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 II‐(3)チムニー部二相流試験とその流動解析‐
AKASHI TOYO, TAKAHASHI MINORU, YAMADA TOORU, HARA KAZUYUKI, KONDO MASATOSHI
日本原子力学会秋の大会予稿集 2004 255 2004.8
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Pb‐Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 I―(7)強制流動鉛ビスマス内におけるCr,Si,Alを含む鋼材の腐食挙動―
KONDO MASATOSHI, TAKAHASHI MINORU, SAWADA NAOKI, HATA KOJI
日本原子力学会春の年会要旨集 42nd 442 2004.3
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Development of Pb-Bi Cooled Direct Contact Boiling Water Fast Reactor (_II_):_-_(3) Experiment of Two-phase Flow in Chimney and Flow Analysis_-_
AKASHI TOYOU, TAKAHASHI MINORU, YAMADA AKIRA, HARA KAZUYUKI, KONDO MASATOSHI
Proceedings of AESJ 2004 ( 0 ) 171 - 171 2004
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流動鉛ビスマス中における鋼材腐食の研究 (1)―鋼材表面の凹凸が酸化被膜形成に与える影響―
KONDO MASASATO, TAKAHASHI MINORU
材料と環境討論会講演集 50th 165 - 168 2003.10
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鉛ビスマス用酸素計の開発(II)
HATA KOJI, HARA KAZUYUKI, SAWADA NAOKI, KONDO MASATOSHI, TAKAHASHI MINORU
日本原子力学会秋の大会予稿集 2003 309 2003.8
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鉛ビスマス環境下における配管破断面の状態観察
KONDO MASATOSHI, TAKAHASHI MINORU, HATA KOJI
日本原子力学会秋の大会予稿集 2003 474 2003.8
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Corrosion Characteristics of Steels and Control Technique of Oxygen Potential in Flowing Lead-bismuth Eutectic.
KONDO MASATOSHI, SAWADA NAOKI, TAKAHASHI MINORU, HATA KOJI, YOSHIDA SUSUMU
日本機械学会年次大会講演論文集 2003 ( Vol.3 ) 241 - 242 2003.8
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Corrosion Characteristics of Steels and Control Technique of Oxygen Potential in Flowing Lead-bismuth Eutectic
KONDO Masatoshi, SAWADA Naoki, TAKAHASHI Minoru, HATA Koji, Yoshida Susumu
年次大会講演論文集 : JSME annual meeting 2003 ( 3 ) 241 - 242 2003.8
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鉛ビスマス用耐熱応力型酸素濃度計の開発
TAKAHASHI MINORU, KONDO MASATOSHI, YOSHIDA SUSUMU, SAWADA NAOKI, MATSUZAKI JUN
日本原子力学会春の年会要旨集 41st 597 2003.3
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鉛ビスマス循環ループのポンプ・流量計の開発
SAWADA NAOKI, TAKAHASHI MINORU, KONDO MASATOSHI
日本原子力学会春の年会要旨集 41st 516 2003.3
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Study for development of Pb-Bi cooled direct contact boiling water small fast reactor (PBWFR)
TAKAHASHI M.
Proc. of Mechanical Engineering Congress, Tokushima, Japan, Aug. 5-8, 2003 3 239 - 240 2003
Awards
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第4回 日本原子力学会材料部会 Best Figure賞
2022.3 一般社団法人 日本原子力学会材料部会 FeCrAl-ODS合金の表面をスクラッチして現れた流れ星にかける願い
宮川幸大, 畑山奨, 菱沼良光, 大野直子, 田中照也, 坂本寛, 近藤正聡
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PITCH Founders Award
2021.9 東京工業大学工学院
今泉瑛介、宮川幸大、正木晴也、北村嘉規、西尾龍乃介、近藤正聡
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令和二年度 核融合炉工学共同研究優秀賞
2021.7 国立研究開発法人 量子科学技術研究開発機構 核融合中性子源照射モジュールの液体金属伝熱媒体と鉄鋼材料の材料共存性に関する実験的研究
近藤正聡、保坂龍広、佐藤聡
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東京工業大学リサーチフェスティバル2018 ベストプレゼンテーション賞
2018.11 東京工業大学 SF映画技術実現化への挑戦、<液体金属アーマーロボット>
近藤正聡
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Masaji Yoshikawa Prize for Fusion Energy
2017.9 Fusion energy forum of JAPAN
Masatoshi KONDO
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Challenging Research Award 2017
2017.7 Tokyo Institute of Technology Experimental study on functional expression of function-sharing interface structure in corrosive fluid environment
Masatoshi KONDO
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H29年度萌芽研究
2017.6 東京工業大学 先導原子力研究所 電気化学的定常診断法による機能性材料の力学的健全性評価
近藤正聡
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東京工業大学「先導原子力研究所」のロゴマーク最優秀賞（採用作品）
2016.12 東京工業大学 先導原子力研究所
近藤正聡
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POSTER PRESENTATION AWARD (INES-5)
2016.11 laboratory for advanced nuclear energy, Tokyo Institute of Technology Oxidation characteristics of lead alloy coolant in air ingress accident
Masatoshi KONDO
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Recognized reviewer- Fusion Engineering and Design
2016.11 Elsevier
Masatoshi KONDO
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Outstanding reviewer- Journal of Nuclear Materials
2016.8 Elsevier
Masatoshi KONDO
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Winner in the ICONE-24 Student Best Paper competition
2016.6 ICONE24 organaizing committee ICONE24-60998 Study on Stability of Liquid Jet for Liquid Lithium Target of Boron Neutron Capture Therapy (BNCT)
Yuki Maehara, Masatoshi KONDO, Minoru TAKAHASHI
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Recognized reviewer - Journal of Nuclear Materials
2016.4 Elsevier
Masatoshi KONDO
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レーザー研シンポジウム2016 ベストポスター賞
2016.4 大阪大学レーザーエネルギー学研究センター共同研究専門委員会 Pb-17Li撹拌流動場における不純物除去に関する研究
近藤正聡, 乗松孝義, 石井政臣, 室賀健夫, NIF
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平成27年度 「研究の種発掘」支援
2015.7 東京工業大学 動的な合金化プロセスによる高温溶融アルカリ金属の瞬時不活性化に関する研究
近藤正聡
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Outstanding Reviewer - Fusion engineering and Design
2015.5 Elsevier
Masatoshi KONDO
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Recognized reviewer - Journal of Nuclear Materials
2014.1 Elsevier
Masatoshi KONDO
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日本原子力学会第５回核融合工学部会賞 奨励賞
2008.9 社団法人日本原子力学会核融合工学部会 液体金属および溶融塩中の腐食機構に関する研究
近藤正聡
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World Nuclear University Fellow
2005.8 World Nuclear University
Masatoshi KONDO
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Best captainship award in COE-INES captainship educational program
2005.1 東京工業大学
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東京工業大学大学院理工学研究科原子核工学専攻優秀修士論文発表賞
2004.3 東京工業大学 Study on Corrosion and Erosion Mechanism of Steels in a Liquid Lead Bismuth
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日本原子力学会秋の大会優秀ポスター発表賞
2003.9 日本原子力学会
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日本原子力学会春の年会優秀ポスター発表賞
2003.3 日本原子力学会
Research Projects
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核融合炉の液体金属ブランケットにおけるMHD圧力損失低減を目指したFeCrAl合金製円管内壁の酸化処理最適化に関する研究
Grant number：20245005 2024.4 - 2025.3
物質・デバイス領域共同研究拠点 次世代若手協働研究課題 次世代若手共同研究
武藤龍平, 松尾保孝, 遠堂敬史, 近藤正聡
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Effect of electromigration on corrosion and mass transfer in high-temperature liquid metals
Grant number：23K17676 2023.6 - 2026.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Challenging Research (Exploratory)
Grant amount：\6370000 （ Direct Cost: \4900000 、 Indirect Cost：\1470000 ）
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FeCrAl-ODSの鉛冷却SMRにおける応力-腐食重畳 環境下の構造健全性工学
Grant number：23K26540 2023.4 - 2026.3
基盤研究(B)
大野直子, 近藤正聡, 笠田竜太
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Structural integrity engineering of FeCrAl-ODS in lead-cooled SMR under superimposed stress-corrosion environment
Grant number：23H01895 2023.4 - 2026.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)
Grant amount：\19110000 （ Direct Cost: \14700000 、 Indirect Cost：\4410000 ）
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Structural integrity engineering of FeCrAl-ODS in lead-cooled SMRs under stress-corrosion superposition
Grant number：23K26588 2023.4 - 2026.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)
Grant amount：\19110000 （ Direct Cost: \14700000 、 Indirect Cost：\4410000 ）
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Experimental study on mitigation of MHD pressure drop by electrical insulating oxide layer having self-maintainability
Grant number：21H01060 2021.4 - 2025.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B) Grant-in-Aid for Scientific Research (B)
Grant amount：\12220000 （ Direct Cost: \9400000 、 Indirect Cost：\2820000 ）
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Experimental study on mitigation of MHD pressure drop by electrical insulating oxide layer having self-maintainability
Grant number：23K20836 2021.4 - 2025.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B)
Grant amount：\12220000 （ Direct Cost: \9400000 、 Indirect Cost：\2820000 ）
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Proposal of the innovative fusion reactor for nuclear transmutation by the utilization of a super fast neutron and the high-level radioactive waste
Grant number：17H06231 2017.6 - 2020.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Challenging Research (Pioneering) Challenging Research (Pioneering)
Hashizume Hidetoshi
Grant amount：\25740000 （ Direct Cost: \19800000 、 Indirect Cost：\5940000 ）
We have proposed a completely new concept of a fusion reactor that combines ultra-high-energy 14 MeV neutrons generated by fusion reactions with high-level waste (fission products and minor actinides) contained in spent nuclear fuel produced by nuclear power plants. We have performed designing of the minor actinide fuel and transmutation system, and also the blanket including the fission products transmutation system. We have indicated successful scenarios that it is possible to surely reduce the domestic storage amount of these high-level wastes by introducing the innovative fusion reactors to Japan.
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Study on method for instantaneous inactivation of liquid alkari metals
Grant number：16K14526 2016.4 - 2019.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Challenging Exploratory Research Grant-in-Aid for Challenging Exploratory Research
Kondo Masatoshi
Grant amount：\3380000 （ Direct Cost: \2600000 、 Indirect Cost：\780000 ）
Liquid alkali metals are promising coolants for innovative nuclear reactors such as fusion reactors and fast reactors. However, they react with air and water violently. The alkali metal fire has been extinguished by covering with dried powders according to the suffocation effect. However, this is not reasonable method, since lkari metals keep their chemical activity and react with air and water without the cover. The large fire according to the accidental leakage of liquid alkali metal coolant in the nuclear reactors should be extinguished by reasonable methods. In the present study, revolutionary method to extinguish alkali metal fire based on the formation of Li alloys. The behaviors of Li and inert metals (i.e., Pb and Sn) in their alloying process were experimentally investigated. Various experiments were performed to make clear the thermophysical and chemical characteristics of the Li alloys.
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Study on function sharing type interface structures and demonstration of self-healing function in corrosive environment for advanced blanket systems of fusion reactors
Grant number：16H04617 2016.4 - 2019.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B) Grant-in-Aid for Scientific Research (B)
KONDO MASATOSHI
Grant amount：\12090000 （ Direct Cost: \9300000 、 Indirect Cost：\2790000 ）
For the development of heat exchanger of liquid breeder blankets and liquid divertors, experimental study on function sharing multiple interface structures which have the function of tritium permeation barrier, corrosion resistance, and self-healing was performed. The multiple interface structures were fabricated by plasm splay and diffusion bonding of ceramic coatings and metal layers, and their tritium permeability and material compatibility with liquid metals were studied. Electrochemical methods were studied to monitor the degradation of the multiple interface structures in liquid metals. The experimental study on the electrochemical impedance spectroscopy and the quartz crystal microbalance under liquid metal conditions were performed to varify their availability for the installation in the liquid breeder blankets and liquid metal divertors.
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Simultaneous monitoring of oxygen potential and interface structure in liquid Pb-Li alloy
Grant number：25820437 2013.4 - 2016.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Young Scientists (B) Grant-in-Aid for Young Scientists (B)
KONDO MASATOSHI
Grant amount：\3380000 （ Direct Cost: \2600000 、 Indirect Cost：\780000 ）
(1) The Pb-Li alloys with various Li concentration were fabricated with the small metal grains of Li and Pb. Small metal grains of Li and Pb should be well mixed before the heating and the melting to prevent the formation of Li rich alloy by the segregation of Li. The chemical behaviors of non-metal impurities in the alloys are investigated by means of temperature programmed desorption method.(2) The electrical characteristics of Y2O3 and ZrO2 in a static Pb were successfully obtained by an electrochemical impedance spectroscopy. The results indicated that the in-situ analysis of the formation and the growth of the oxide layers in a liquid metal can be done by the EIS method. (3) The solid electrolyte sensor and the specimen of pre-oxidized zirconium (Zr) were simultaneously immersed to liquid Pb at 698-898K. The responses of the sensor and the EIS were successfully obtained, and these signals indicated that the Zr oxide layer is chemically stable in liquid Pb.
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Evaluation and improvement of properties of hydride shielding materials for a fusion reactor
Grant number：25289344 2013.4 - 2016.3
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B) Grant-in-Aid for Scientific Research (B)
Tanaka Teruya, SAGARA Akio, HISHINUMA Yoshimitsu, KONDO Masatoshi, YOSHINO Masahito, SAKAUE Hiroyuki, MUTA Hiroaki, TAMURA Hitoshi
Grant amount：\10530000 （ Direct Cost: \8100000 、 Indirect Cost：\2430000 ）
Test fabrication of hydride blocks using commercially available ZrH2 and TiH2 powders were performed by the cold isostatic press (CIP) process (typical dimensions: ~2.5x2.5x2.5cm3, 398MPa). The obtained densities were ~80% and 85% compared with the theoretical densities, respectively. The effective density of the hydride component increased to ~95 % by using a Cu-coated TiH2 powder and die pressing. This could be a potential method for the densification of the blocks. Thermal desorption spectroscopy (TDS) data of the hydride powders were obtained in high vacuum, Ar, He+H2 and air environment to investigate the hydrogen retention properties under accidental conditions. Effective positions of hydride blocks in a fusion reactor, form of use and atmosphere control were proposed based on the results. The hydrogen release temperature of the ZrH2 material was significantly decreased due to oxidation in air.
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液体金属鉛リチウム場における溶存酸素・材料界面特性の同時評価
2013 - 2015
文部科学省 科学研究費補助金(若手研究(B))
近藤 正聡
Authorship：Principal investigator Grant type：Competitive
Grant amount：\3380000 （ Direct Cost: \2600000 、 Indirect Cost：\780000 ）
液体金属鉛静止場における浸漬材料の表面酸化挙動を、電気化学インピーダンス法を用いてオンライン評価した。試験材料として、核融合炉の候補構造材料である低放射化フェライト鋼JLF-1(Fe-9Cr-2W-0.1C)やSUS316(Fe-18Cr-12Ni-2Mo)、これらの鋼材構成元素である鉄とクロム、表面に酸化物が形成された場合に機能性材料（水素透過防止膜や絶縁被覆）としての機能が期待されるイットリウム、エルビウム、ジルコニウム、アルミニウムを用いた。30ccの液体鉛をアルミナ坩堝に充填し、環境雰囲気を空気もしくはAr(純度99.999%)の条件で、試験材料の短冊状試験片を電極として浸漬し、接液界面の構造を電気化学インピーダンス法により評価した。参照極としてSUS316ワイヤーを浸漬した。測定結果をボード線図とナイキスト線図として表し、時定数などの情報から、接液界面に形成された酸化被膜の物性、膜厚、クラックの有無などを評価した。浸漬測定試験後、電極の表層に形成された酸化物の金相観
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核融合炉水素化物遮蔽ブロックの水素保持特性評価および特性向上・長寿命化の研究
2013 - 2015
文部科学省 科学研究費補助金(基盤研究(B))
田中 照也
Grant type：Competitive
Grant amount：\10530000 （ Direct Cost: \8100000 、 Indirect Cost：\2430000 ）
本研究課題では、水素化物粉末プレスによるブロック体を試作し、その水素保持特性の評価と特性向上を目指している。今年度、本研究で使用する市販TiH2、ZrH2粉末材料についてTG－DTA測定を行い、水素含有量、高温での水素脱離、及び、酸化特性に関する基礎データを確認した。また、ブロック試作の第一段階として、超硬ダイスを用いた室温プレス成型により10mmφx1~2mm厚のディスクを試作した。この手法によりTiH2、ZiH2ディスクの密度を理論密度の90％程度とするための圧力は、各々、900MPa、1200MPaであった。室温から350℃までの熱伝導率については、14W/m/Kと7W/m/K程度であり、バルク水素化物の熱伝導率の文献値と比較して、各々約70％、10％であった。これら基礎データは、今後のブロック大型化の検討や核融合炉における水素化物中性子遮蔽体の特性評価、除熱設計に利用するとともに、高密度化、水素保持・熱伝導特性向上の研究を推進する。本課題における水素保持安定性評価の際
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Extension of high temperature life time of low activation vanadium alloys by nano-particle control
Grant number：22360392 2010 - 2012
Ministry of Education, Culture, Sports, Science and Technology Grants-in-Aid for Scientific Research(基盤研究(B)) Grant-in-Aid for Scientific Research (B)
Takeo MUROGA
Grant type：Competitive
Grant amount：\17550000 （ Direct Cost: \13500000 、 Indirect Cost：\4050000 ）
For the purpose of enhancing high temperature strength and upper operation temperature limit of low activation vanadium alloys, which are promising candidate of fusion structural materials, production of V-4Cr-4Ti alloys containing high density precipitates and high density nano-particles was performed by repeated thermo-mechanical treatments and mechanical alloying, respectively. Mechanical property evaluation including thermal creep tests verified the increased high temperature strength by the precipitates or nano-particles, and the underlying mechanisms were clarified.
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Extension of high temperature life time of low activation vanadium alloys by nano-particle control
Grant number：22360392 2010 - 2012
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (B) Grant-in-Aid for Scientific Research (B)
MUROGA Takeo, NAGASAKA Takuya, HISHINUMA Yoshimitsu, YAGI Juro
Grant amount：\17550000 （ Direct Cost: \13500000 、 Indirect Cost：\4050000 ）
For the purpose of enhancing high temperature strength and upper operation temperature limit of low activation vanadium alloys, which are promising candidate of fusion structural materials, production of V-4Cr-4Ti alloys containing high density precipitates and high density nano-particles was performed by repeated thermo-mechanical treatments and mechanical alloying, respectively. Mechanical property evaluation including thermal creep tests verified the increased high temperature strength by the precipitates or nano-particles, and the underlying mechanisms were clarified.
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2009 - 2012
Ministry of Education, Culture, Sports, Science and Technology Grants-in-Aid for Scientific Research(基盤研究(A))
Akio SAGARA
Grant type：Competitive
Grant amount：\45760000 （ Direct Cost: \35200000 、 Indirect Cost：\10560000 ）
Flinak loop system Orosh2i-1 has been designed and constructed as the world’s first apparatus for performing experiments on separate recovery of hydrogen and heat under circulation condition of a molten salt cooled blanket system. Development and studies on a centrifugal pump for high temperature (>500 oC) Flinak, hydrogen sensor, hydrogen recovery module, hydrogen permeation barrier coating, anti-corrosion coating, hydrogen absorption and release properties in Flinak, etc. have been successfully advanced for establishment of a self-cooled molten salt blanket system with high inherent safety.
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Experimental study on separate recovery of hydrogen and heat from molten salt circulation system for establishment of liquid blanket system
Grant number：21246141 2009 - 2012
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (A) Grant-in-Aid for Scientific Research (A)
SAGARA Akio, NISHIMURA Arata, MUROGA Takeo, NAGASAKA Takuya, TANAKA Teruya, HISHINUMA Yoshimitsu, GOTO Takuya, KONDO Masatoshi, YAGI Juro, WATANABE Takashi, FUKADA Satoshi
Grant amount：\45760000 （ Direct Cost: \35200000 、 Indirect Cost：\10560000 ）
Flinak loop system Orosh2i-1 has been designed and constructed as the world’s first apparatus for performing experiments on separate recovery of hydrogen and heat under circulation condition of a molten salt cooled blanket system. Development and studies on a centrifugal pump for high temperature (>500 oC) Flinak, hydrogen sensor, hydrogen recovery module, hydrogen permeation barrier coating, anti-corrosion coating, hydrogen absorption and release properties in Flinak, etc. have been successfully advanced for establishment of a self-cooled molten salt blanket system with high inherent safety.
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Study on corrosion in metal vapor atmosphere in fusion blanket
Grant number：21760695 2009 - 2010
Ministry of Education, Culture, Sports, Science and Technology Grants-in-Aid for Scientific Research(若手研究(B)) Grant-in-Aid for Young Scientists (B)
Masatoshi KONDO
Authorship：Principal investigator Grant type：Competitive
Grant amount：\3380000 （ Direct Cost: \2600000 、 Indirect Cost：\780000 ）
Liquid metals and molten salts are considered as a coolant and a tritium breeder for the blanket systems of fusion reactors. The purpose of the present study is to investigate the fundamental characteristics of metal vapor generated from the liquid breeders and the corrosion of materials in the vapor atmosphere. The experimental apparatus, which can apply to the corrosion tests, were developed. This apparatus equipped the function for the measurement of vapor pressure. For the corrosion analysis, the method for the measurement of metal elements adhered on a specimen surface due to the corrosion in the vapor atmosphere were established.
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Study on corrosion in metal vapor atmosphere in fusion blanket
Grant number：21760695 2009 - 2010
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Young Scientists (B) Grant-in-Aid for Young Scientists (B)
KONDO Masatoshi
Grant amount：\3380000 （ Direct Cost: \2600000 、 Indirect Cost：\780000 ）
Liquid metals and molten salts are considered as a coolant and a tritium breeder for the blanket systems of fusion reactors. The purpose of the present study is to investigate the fundamental characteristics of metal vapor generated from the liquid breeders and the corrosion of materials in the vapor atmosphere. The experimental apparatus, which can apply to the corrosion tests, were developed. This apparatus equipped the function for the measurement of vapor pressure. For the corrosion analysis, the method for the measurement of metal elements adhered on a specimen surface due to the corrosion in the vapor atmosphere were established.
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液体ブランケット用水素(同位体)センサー・ポンプの電極高度化研究
Grant number：20049008 2008 - 2009
日本学術振興会 科学研究費助成事業 特定領域研究 特定領域研究
近藤 正聡, 田中 将裕, 室賀 健夫
Grant amount：\2000000 （ Direct Cost: \2000000 ）
核融合炉の液体増殖材ブランケット中に溶解している水素・水素同位体の量をオンラインでモニタリングする手段として、固体電解質水素センサの電極の開発研究を実施した。液体増殖ブランケットのような腐食・還元雰囲気下で固体電解質を水素センサとして機能させるためには、固体電解質表面を保護する必要がある。そこでパラジウム(Pd)の高い水素透過性に着目した。まず、腐食に対する保護性を有するような緻密膜状電極を形成するために、Pdの塗布方法や適切な熱処理条件を調べた。この保護性を腐食試験により確認した上で、電極として固体電解質表面に取り付けて水素・アルゴン混合ガス雰囲気中で試験し、その機能を調べた。センサ起電力はネルンストの式で評価される理論起電力に良く合致する事がわかった。これにより、Pd緻密膜電極は、従来使用されてきたPt電極と同様に、電極として安定に機能する事がわかった。Pd緻密膜電極の電極反応のメカニズムを調べた結果、緻密膜電極と固体電解質との界面における3相界面により電極反応が生じていることがわかった。更に、この電極を塗布した固体電解質水素センサを液体増殖材Flinak中に浸漬し、水素濃度のオンライン試験を実施した。Flinak中の水素濃度を、Flinak自由液面の気液平衡により制御したところ、そのセンサ起電力はネルンストの式で評価される理論起電力に良く合致した。つまり、本研究で開発したPd緻密膜電極を用いたことによりFlinak中の水素濃度の測定に成功したといえる。
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液体ブランケット用水素(同位体)センサー・ポンプの電極高度化研究
Grant number：20049008 2008 - 2009
文部科学省 科学研究費補助金(特定領域研究) 特定領域研究
近藤 正聡
Authorship：Principal investigator Grant type：Competitive
Grant amount：\2000000 （ Direct Cost: \2000000 ）
核融合炉の液体増殖材ブランケット中に溶解している水素・水素同位体の量をオンラインでモニタリングする手段として、固体電解質水素センサの電極の開発研究を実施した。液体増殖ブランケットのような腐食・還元雰囲気下で固体電解質を水素センサとして機能させるためには、固体電解質表面を保護する必要がある。そこでパラジウム(Pd)の高い水素透過性に着目した。まず、腐食に対する保護性を有するような緻密膜状電極を形成するために、Pdの塗布方法や適切な熱処理条件を調べた。この保護性を腐食試験により確認した上で、電極として固体電解質表面に取り付けて水素・アルゴン混合ガス雰囲気中で試験し、その機能を調べた。センサ起電力はネルンストの式で評価される理論起電力に良く合致する事がわかった。これにより、Pd緻密膜電極は、従来使用されてきたPt電極と同様に、電極として安定に機能する事がわかった。Pd緻密膜電極の電極反応のメカニズムを調べた結果
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Grant number：19206100 2007 - 2009
Ministry of Education, Culture, Sports, Science and Technology Grants-in-Aid for Scientific Research(基盤研究(A)) Grant-in-Aid for Scientific Research (A)
Takeo MUROGA
Grant type：Competitive
Grant amount：\41990000 （ Direct Cost: \32300000 、 Indirect Cost：\9690000 ）
Compatibility between candidate liquid metal breeders of liquid Li and Li-Pb and candidate low activation structural materials of Reduced Activation Ferritic Steel (JLF-1) and vanadium alloys, and materials property change were investigated for fusion blanket application. In particular, difference between static and flowing conditions, effects of impurity N, O and C and mass transfer to the surrounding materials were clarified, providing suggestion on the mass transfer control of the blanket systems.
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Dynamic mass transfer between low activation materials and liquid metal breeders, and materials soundness
Grant number：19206100 2007 - 2009
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Scientific Research (A) Grant-in-Aid for Scientific Research (A)
MUROGA Takeo, NAGASAKA Takuya, TANAKA Teruya, KONDO Masatoshi, HISHINUMA Yoshimitsu
Grant amount：\41990000 （ Direct Cost: \32300000 、 Indirect Cost：\9690000 ）
Compatibility between candidate liquid metal breeders of liquid Li and Li-Pb and candidate low activation structural materials of Reduced Activation Ferritic Steel (JLF-1) and vanadium alloys, and materials property change were investigated for fusion blanket application. In particular, difference between static and flowing conditions, effects of impurity N, O and C and mass transfer to the surrounding materials were clarified, providing suggestion on the mass transfer control of the blanket systems.
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Development of on-line hydrogen sensor for liquid blanket system
Grant number：19760599 2007 - 2008
Japan Society for the Promotion of Science Grants-in-Aid for Scientific Research Grant-in-Aid for Young Scientists (B) Grant-in-Aid for Young Scientists (B)
KONDO Masatoshi
Grant amount：\3750000 （ Direct Cost: \3300000 、 Indirect Cost：\450000 ）
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Development of on-line hydrogen sensor for liquid blanket system
Grant number：19760599 2007 - 2008
Ministry of Education, Culture, Sports, Science and Technology Grants-in-Aid for Scientific Research(若手研究(B)) Grant-in-Aid for Young Scientists (B)
Masatoshi KONDO
Authorship：Principal investigator Grant type：Competitive
Grant amount：\3750000 （ Direct Cost: \3300000 、 Indirect Cost：\450000 ）
Media Coverage
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Selecting the right structural materials for fusion reactors
2022.2