Masayuki Takeuchi - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101014242428115
researchmap Member ID: R000023928

Research Areas

Energy / Nuclear engineering /

Papers

Ion beam induced luminescence analysis of europium complexes in styrene-divinylbenzene copolymer-coated spherical silica by proton and argon ion beams irradiation

Nakahara Masaumi, Watanabe So, Takeuchi Masayuki, Yuyama Takahiro*, Ishizaka Tomohisa*, Ishii Yasuyuki*, Yamagata Ryohei*, Yamada Naoto*, Koka Masashi*, Kada Wataru* …

Nuclear Instruments and Methods in Physics Research B, 542 144-150, Sep, 2023 Peer-reviewed
Development of engineering scale extraction chromatography separation system, 2; Spray drying granulation of silica support for adsorbent

Hasegawa Kenta, Goto Ichiro*, Miyazaki Yasunori, Ambai Hiromu, Watanabe So, Watanabe Masayuki, Sano Yuichi, Takeuchi Masayuki

Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 5, May, 2023 Peer-reviewed
Design of MA(III)/Ln(III) separation process of extraction chromatography technology

Akuzawa Tadashi*, Kim S.-Y.*, Kubota Masahiko*, Wu H.*, Watanabe So, Sano Yuichi, Takeuchi Masayuki, Arai Tsuyoshi*

Journal of Radioanalytical and Nuclear Chemistry, 331(12) 5851-5858, Dec, 2022 Peer-reviewed
Sodium-cooled Fast Reactors

Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka …

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631, Jul, 2022 Peer-reviewed
Acid dissociation constant of bis(2-ethylhexyl) hydrogen phosphate impregnated in a polymer layer coated on silica microparticles

Miyagawa Akihisa*, Takeuchi Masayuki, Arai Tsuyoshi*, Watanabe So, Sano Yuichi, Nakatani Kiyoharu*

Bulletin of the Chemical Society of Japan, 95(4) 566-568, Apr, 2022 Peer-reviewed
Development of MA separation process with TEHDGA/SiO$_{2}$-P for an advanced reprocessing

Horiuchi Yusuke, Watanabe So, Sano Yuichi, Takeuchi Masayuki, Kida Fukuka*, Arai Tsuyoshi*

Journal of Radioanalytical and Nuclear Chemistry, 330(1) 237-244, Oct, 2021 Peer-reviewed
Improvement in flow-sheet of extraction chromatography for trivalent minor actinides recovery

Watanabe So, Senzaki Tatsuya, Shibata Atsuhiro, Nomura Kazunori, Takeuchi Masayuki, Nakatani Kiyoharu*, Matsuura Haruaki*, Horiuchi Yusuke*, Arai Tsuyoshi*

Journal of Radioanalytical and Nuclear Chemistry, 322(3) 1273-1277, Dec, 2019 Peer-reviewed
Extraction mechanism of lanthanide ions into silica-based microparticles studied by single microparticle manipulation and microspectroscopy

Otaka Toshiki*, Sato Tatsumi*, Ono Shimpei, Nagoshi Kohei, Abe Ryoji*, Arai Tsuyoshi*, Watanabe So, Sano Yuichi, Takeuchi Masayuki, Nakatani Kiyoharu*

Analytical Sciences, 35(10) 1129-1133, Oct, 2019 Peer-reviewed
Characteristics of TPDN/SiO$_{2}$-P adsorbent for MA(III) recovery

Kofuji Hirohide, Watanabe So, Takeuchi Masayuki, Suzuki Hideya, Matsumura Tatsuro, Shiwaku Hideaki, Yaita Tsuyoshi

Progress in Nuclear Science and Technology (Internet), 5 61-65, Nov, 2018 Peer-reviewed
Simulation of fluidity, dispersion and mass transfer in an annular centrifugal contactor

Sano Yuichi, Sakamoto Atsushi, Takeuchi Masayuki, Misumi Ryuta*, Kunii Kanako*, Todoroki Kei*, Nishi Kazuhiko*, Kaminoyama Meguru*

Kagaku Kogaku Rombunshu, 44(6) 335-340, Nov, 2018 Peer-reviewed
Corrosion behaviour of FeCrAl-ODS steels in nitric acid solutions with several temperatures

Takahatake Yoko, Ambai Hiromu, Sano Yuichi, Takeuchi Masayuki, Koizumi Kenji, Sakamoto Kan*, Yamashita Shinichiro

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 9, Oct, 2018 Peer-reviewed
CFD analysis for U extraction in a centrifugal contactor

Sano Yuichi, Sakamoto Atsushi, Kofuji Hirohide, Takeuchi Masayuki

Proceedings of 21st Pacific Basin Nuclear Conference (PBNC 2018) (USB Flash Drive), 314-318, Sep, 2018 Peer-reviewed
Flow behavior in annular centrifugal extractors with different vessel sizes

Misumi Ryuta*, Todoroki Kei*, Kunii Kanako*, Nishi Kazuhiko*, Kaminoyama Meguru*, Sano Yuichi, Sakamoto Atsushi, Takeuchi Masayuki

Kagaku Kogaku Rombunshu, 44(5) 285-291, Sep, 2018 Peer-reviewed
Am, Cm recovery from genuine HLLW by extraction chromatography

Watanabe So, Sano Yuichi, Kofuji Hirohide, Takeuchi Masayuki, Shibata Atsuhiro, Nomura Kazunori

Journal of Radioanalytical and Nuclear Chemistry, 316(3) 1113-1117, Jun, 2018 Peer-reviewed
Rotor speed and supply flow rate effects on flow behavior in an annular centrifugal extractor

Misumi Ryuta*, Kunii Kanako*, Todoroki Kei*, Nishi Kazuhiko*, Kaminoyama Meguru*, Sano Yuichi, Sakamoto Atsushi, Takeuchi Masayuki

Kagaku Kogaku Rombunshu, 44(3) 135-141, May, 2018 Peer-reviewed
Partitioning of plutonium by acid split method with dissolver solution derived from irradiated fast reactor fuel with high concentration of plutonium

Nakahara Masaumi, Sano Yuichi, Nomura Kazunori, Takeuchi Masayuki

Journal of Chemical Engineering of Japan, 51(3) 237-242, Mar, 2018 Peer-reviewed
Corrosion behavior of ODS steels with several chromium contents in hot nitric acid solutions

Tanno Takashi, Takeuchi Masayuki, Otsuka Satoshi, Kaito Takeji

Journal of Nuclear Materials, 494(494) 219-226, Oct, 2017 Peer-reviewed
Effect of chloride ion on corrosion behavior of SUS316L-grade stainless steel in nitric acid solutions containing seawater components under $\gamma$-ray irradiation

Sano Yuichi, Ambai Hiromu, Takeuchi Masayuki, Iijima Shizuka, Uchida Naoki

Journal of Nuclear Materials, 493 200-206, Sep, 2017 Peer-reviewed
Micro-PIXE analysis on adsorbent of extraction chromatography for MA(III) recovery

Takahatake Yoko, Watanabe So, Kofuji Hirohide, Takeuchi Masayuki, Nomura Kazunori, Sato Takahiro*

International Journal of PIXE, 26(3\&4) 73-83, Sep, 2017 Peer-reviewed
Minor actinides recovery from irradiated fuel for SmART cycle test

Takeuchi Masayuki, Sano Yuichi, Watanabe So, Nakahara Masaumi, Aihara Haruka, Kofuji Hirohide, Koizumi Tsutomu, Mizuno Tomoyasu

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6, Apr, 2017 Peer-reviewed

Misc.

Evaluation of the mass transfer coefficients for the minor actinide separation; Evaluation by the single drop method

Sakamoto Atsushi, Kibe Satoshi*, Kawanobe Kazunori*, Fujisaku Kazuhiko*, Sano Yuichi, Takeuchi Masayuki, Suzuki Hideya*, Tsubata Yasuhiro, Ban Yasutoshi, Matsumura Tatsuro

JAEA-Research 2021-003, 30, Jun, 2021
Actinides recovery from irradiated fuel for SmART cycle

Sano Yuichi, Watanabe So, Nakahara Masaumi, Aihara Haruka, Takeuchi Masayuki

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 4, Sep, 2017
Countercurrent extraction/stripping experiments using TDdDGA solvent extractant in a centrifugal contactor system,2; Evaluation on the improved flowsheet for MA recovery

Kibe Satoshi, Fujisaku Kazuhiko*, Sakamoto Atsushi, Sano Yuichi, Takeuchi Masayuki, Suzuki Hideya, Tsubata Yasuhiro, Matsumura Tatsuro

JAEA-Research 2016-024, 2016(24) 40-2,1-40, Feb, 2017
Corrosion behavior of SUS316L in nitric acid solution containing seawater components

Sano Yuichi, Ambai Hiromu, Takeuchi Masayuki, Iijima Shizuka, Uchida Naoki

Proceedings of European Corrosion Congress 2016 (EUROCORR 2016) (USB Flash Drive), 10, Sep, 2016
Countercurrent extraction/stripping experiments using TDdDGA solvent extractant in a centrifugal contactors system

Kibe Satoshi, Fujisaku Kazuhiko*, Ambai Hiromu, Sakamoto Atsushi, Sano Yuichi, Takeuchi Masayuki, Suzuki Hideya, Tsubata Yasuhiro, Matsumura Tatsuro

JAEA-Research 2015-021, 2015(21) 40-2,1-40, Feb, 2016
Irradiation degradation of adsorbents for minor actinides recovery

Watanabe So, Sano Yuichi, Kofuji Hirohide, Takeuchi Masayuki, Koizumi Tsutomu

NEA/NSC/R(2015)2 (Internet), 338-344, Jun, 2015
Dissolutions of oxide dispersion strengthened ferritic steels in various nitric acid solutions; Martensitic 9Cr-ODS steels

Inoue Masaki, Ikeuchi Hirotomo, Takeuchi Masayuki, Koyama Shinichi, Suto Mitsuo

JAEA-Research 2011-057, 2011(57) 100-2,1-100, Mar, 2012
Salt-free technique for solvent washing process in NEXT process

Sano Yuichi, Kaji Naoya, Shibata Atsuhiro, Takeuchi Masayuki, Washiya Tadahiro

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 7, Dec, 2011
FaCT Phase I evaluation on the advanced aqueous reprocessing process, 5; Research and development of uranium crystallization system

Shibata Atsuhiro, Yano Kimihiko, Sambommatsu Yuji, Nakahara Masaumi, Takeuchi Masayuki, Washiya Tadahiro, Nagata Masanobu*, Chikazawa Takahiro*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6, Dec, 2011
Corrosion study on cold crucible for pyrochemical reprocessing of spent nuclear fuel

Takeuchi Masayuki, Arai Yoichi, Kase Takeshi, Koizumi Tsutomu

Proceedings of International Symposium on EcoTopia Science 2007 (ISETS '07) (CD-ROM), 1084-1088, Nov, 2007
Development of centrifugal contactor with high reliability

Okamura Nobuo, Takeuchi Masayuki, Ogino Hideki, Kase Takeshi, Koizumi Tsutomu

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), 1070-1075, Sep, 2007
Development of centrifugal contactor system in JNC

Washiya Tadahiro, Takeuchi Masayuki, Ogino Hideki, Aose Shinichi

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6, Oct, 2005
Corrosion Resistance of Ceramic Materials in Pyrochemical Reprocessing Condition by Using Molten Salt for Spent Nuclear Oxide Fuel

Takeuchi Masayuki, Hanada Keiji, Aose Shinichi, Koizumi Tsutomu, Kato Toshihiro*

Journal of Physics and Chemistry of Solids, 66(2-4) 521-525, Jan, 2005
Corrosion Resistance of Ceramic Materials in Pyrochemical Electrowinning Condition

Takeuchi Masayuki, Kato Toshihiro*, Washiya Tadahiro, Takashi Suganuma, Aose Shinichi

Saikuru Kiko Giho, (23) 31-40, Jan, 2004
New Decladding System in the Reprocessing Process for Fast Reactor Fuel

Yamada Seiya, Washiya Tadahiro, Takeuchi Masayuki, Suganuma Takashi, Aose Shinichi

Proceedings of 12th International Conference on Nuclear Engineering (ICONE-12) (CD-ROM), 8, Jan, 2004
Effect of Endgrain Attack on Corrosion of 18Cr-10Ni Austenitic Stainless Steel in Simulated Dissolver Liquor

Takeuchi Masayuki, Whillock G. O.*

Journal of Nuclear Science and Technology, 41(6) 702-708, Jan, 2004
Research on in-situ measurement technique of three-dimensional distance

Shiroishi Masatake*, Aoshima Shinichi*, Aose Shinichi, Takeuchi Masayuki

JNC TY8400 2003-007, 43, Apr, 2003
Corrosion Resistance of Ceramic Materials in Pyrochemical Reprocessing Condition by using Molten Salt for Spent Nuclear Oxide Fuel

Takeuchi Masayuki, Koizumi Tsutomu, Kato Toshihiro*

Zairyo To Kankyo, 52(6) 299-307, Jan, 2003
None

Washiya Tadahiro, Ogino Hideki, Takeuchi Masayuki, Suganuma T., Aose Shinichi

Saikuru Kiko Giho, (21) 23-32, Jan, 2003
Corrosion resistance of ceramic materials in pyrochemical reprocessing atmosphere by using molten salt for spent nuclear oxide fuel; Corrosion research under chlorine gas condition.

Kato Toshihiro*, Hanada Keiji, Aose Shinichi

JNC TN8430 2002-004, 32, Dec, 2002

Presentations

163

Current status of technology development for LWR-MOX reprocessing

Takeuchi Masayuki

日本原子力学会第18回再処理・リサイクル部会セミナー
Adsorption/elution performance of TEHDGA/SiO$_{2}$-P for Am/Cm Recovery from genuine HLLW

Sato Daisuke, Watanabe So, Arai Yoichi, Nakamura Masahiro, Arai Tsuyoshi*, Sano Yuichi, Shibata Atsuhiro, Takeuchi Masayuki

16th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (IEMPT16)
Basic research programs of vitrification technology for waste volume reduction, 123; Study of removal method of adsorbed interfering elements by metastannic acid

Ichihara Hirotsugu*, Katsuki Kenta*, Arai Tsuyoshi*, Watanabe So, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年秋の大会
Basic research programs of vitrification technology for waste volume reduction, 122; Examination of MA separation process conditions using TEHDGA and HONTA adsorbents

Katsuki Kenta*, Ishizawa Kenta*, Arai Tsuyoshi*, Watanabe So, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年秋の大会
Research program of technical base for spent MOX fuels reprocessing, 2; Nitric acid dissolution test of non-irradiated MOX pellets

Kimura Shuya, Aihara Haruka, Nakahara Masaumi, Yano Kimihiko, Kitawaki Shinichi, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年秋の大会
Research program of technical base for spent MOX fuels reprocessing, 1; Overview and MOX fuel fabrication

Takeuchi Masayuki, Nomura Kazunori, Ishio Takahiro*, Niitsu Yoshinobu*

日本原子力学会2023年秋の大会
Basic research programs of vitrification technology for waste volume reduction, 124; Study of decomposition and regeneration methods for spent adsorbent

Saito Izumi*, Shinoda Tsuyoshi*, Arai Tsuyoshi*, Miyazaki Yasunori, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年秋の大会
Path forward for development of advanced reactor and nuclear fuel cycle technologies

Takeuchi Masayuki

日本原子力学会2023年春の年会
Current status of nuclear fuel cycle technology development

Takeuchi Masayuki

日本原子力学会2023年春の年会
Basic research programs of vitrification technology for waste volume reduction, 115; Study on the polymer coating for improving MA separation performance by extraction chromatography

Kaminaga Daisuke*, Ago Tomohiro*, Fukumoto Hiroki*, Miyazaki Yasunori, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年春の年会
Investigation of the styrene-divinylbenzene coating carrier for extraction chromatography

Kaminaga Daisuke*, Ago Tomohiro*, Fukumoto Hiroki*, Miyazaki Yasunori, Sano Yuichi, Takeuchi Masayuki

第33回日本化学会関東支部茨城地区研究交流会
Hybrid process combining solvent extraction and low pressure loss extraction chromatography for a reasonable MA recovery, 12; Cold test evaluation of the MA+Ln recovery flowsheet

Sakamoto Atsushi, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2022年秋の大会
Hybrid process combining solvent extraction and low pressure loss extraction chromatography for a reasonable MA recovery, 13; Investigation and evaluation of flowsheet for MA + Ln recovery in hot experiment

Nakahara Masaumi, Sakamoto Atsushi, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2022年秋の大会
Study on the electronic structure of HMNTA as a model extractant for minor actinide recovery

Miyazaki Yasunori, Sano Yuichi, Takeuchi Masayuki, Hoshino Masamitsu*, Gejo Tatsuo*, Adachi Junichi*

第16回分子科学討論会(2022横浜)
Development of the Co-processing process with the centrifugal contactor

Sakamoto Atsushi, Sato Takehiko, Sano Yuichi, Takeuchi Masayuki

International Solvent Extraction Conference 2022 (ISEC 2022)
Minor actinides recovery from high level liquid waste using extraction chromatography

Takeuchi Masayuki, Sano Yuichi, Watanabe So

International Conference on Nuclear Fuel Cycle; Sustainable Energy Beyond the Pandemic (GLOBAL 2022)
Adsorption/elution performance of TEHDGA/SiO$_{2}$-P for Am/Cm Recovery from genuine HLLW

Sato Daisuke, Watanabe So, Arai Yoichi, Nakamura Masahiro, Arai Tsuyoshi*, Sano Yuichi, Shibata Atsuhiro, Takeuchi Masayuki

16th NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (IEMPT-16)
Basic research programs of vitrification technology for waste volume reduction, 115; Study on the polymer coating for improving MA separation performance by extraction chromatography

Kaminaga Daisuke*, Ago Tomohiro*, Fukumoto Hiroki*, Miyazaki Yasunori, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2023年春の年会
Investigation of the inhibition effect by adding a ZMH seeding crystal under the existence of Te

Sue Kasumi*, Hirasawa Izumi*, Miyazaki Yasunori, Takeuchi Masayuki

化学工学会第87年会
Basic research programs of vitrification technology for waste volume reduction, 99; Radiation impact assessment on mechanical property of rubber materials for improving devices durability of MA separation system by extraction chromatography

Hasegawa Kenta, Ambai Hiromu, Watanabe So, Okamura Nobuo, Watanabe Masayuki, Sano Yuichi, Takeuchi Masayuki

日本原子力学会2022年春の年会

Industrial Property Rights

7066091 希土類元素及び/又はアクチノイドの吸着材、それを用いた希土類元素及び/又はアクチノイドの回収方法並びにそれを用いたスカンジウム又はアクチノイドの分離方法

松村達郎, 鈴木英哉, 渡部創, 竹内正行, 小藤博英, 国井茂*, 吉田貴昌*
6882654 金属元素の選択的分離方法、及び分離装置

大野真平, 渡部創, 佐野雄一, 小藤博英, 竹内正行, 新井剛*, 松浦治明*, 中谷清治*
6829457 遠心抽出器

坂本淳志, 大畠史一, 竹内正行, not registered
6343760 液中からの放射性元素の分離・除去方法

北垣徹, 星野貴紀, 三本松勇二, 矢野公彦, 竹内正行, not registered
02284064 METHOD AND DEVICE FOR REMOVING SPENT NUCLEAR FUEL CLADDING

山田誠也, 竹内正行, 小泉務, 高見和男*, 須山和昌*, 原輝夫*
2005-043331 使用済核燃料の脱被覆方法及び脱被覆装置

山田誠也, 竹内正行, 小泉務, 高見和男*, 須山和昌*, 原輝夫*
7143969 DECLADDING METHOD AND DECLADDING DEVICE FOR SPENT NUCLEAR FUEL REPROCESSING

山田誠也, 竹内正行, 小泉務, 高見和男*, 須山和昌*, 原輝夫*
1496520 DECLADDING METHOD AND DECLADDING DEVICE FOR SPENT NUCLEAR FUEL REPROCESSING

山田誠也, 竹内正行, 小泉務, 高見和男*, 須山和昌*, 原輝夫*
1496520 Methode et dispositif de dechemisage pour le traitement de combustible nucleaire use

山田誠也, 竹内正行, 小泉務, 高見和男*, 須山和昌*, 原輝夫*
3861286 放射性汚染金属の溶融処理方法

山田誠也, 竹内正行, 小泉務, 村田実*, 草場一夫*
2891945 冷却システム

永井崇之, 竹内正行, 加藤利弘*
H07-043291 吸光分析用プローブ

竹内正行, 永井崇之, 武田誠一郎, 加藤利弘*