Updated on 2026/08/14

写真a

 
OKAMURA TOMOHIRO
 
Organization
Institute of Integrated Research Laboratory for Zero-Carbon Energy Specially Appointed Assistant Professor
Title
Specially Appointed Assistant Professor
Profile

長崎原爆被爆3世という生立ちと、学部生時に福島第一原周辺をヒッチハイクで訪れたことを契機にエネルギー分野、特に原子力に強い関心を抱く。修士課程から本格的に原子力を学びはじめ、博士後期課程では統合的な核燃料サイクルシミュレーターNMB4.0の開発や将来の原子力発電シナリオについて研究。原子力のみならずエネルギー分野全体を鳥瞰できるような専門家になることが目標。

博士後期課程修了後は、株式会社日立製作所に入社後、日立GEニュークリア・エナジー株式会社に出向。原子力技術部で東海第二原子力発電所の再稼働プロジェクトに従事。本当に多くの先輩方から沢山指導いただき、社会人として成長する機会となった。この時にボディービルを本格的に開始し、「Dr. Norkin」という称号を得る。

2023年6月~東京工業大学に移動し、原子力に関連する幅広い研究を展開中。最近は海事産業における原子力エネルギー利用に関する研究が面白い。

国際原子力機関IAEAで開催された37歳以下の研究コンペでWinner of Winners(最優秀賞)獲得(博士1年時)。ボディービルダー。東京工業大学 教職員野球部PHOENIX 所属。諸量評価の研究コミュニティTEAM NMB。核燃料サイクルのデジタルツインプロジェクトNEUChain首謀。

External link

Degree

  • Doctor of nuclear engineering ( Tokyo Institute of Technology )

Research Interests

  • Nuclear Energy System

  • Scenario study on nuclear energy generation

  • Nuclear fuel cycle

  • Geological disposal of high level radioactive waste

  • Blockchain

  • knowledge management

  • Radioactive waste management

Research Areas

  • Manufacturing Technology (Mechanical Engineering, Electrical and Electronic Engineering, Chemical Engineering) / Design engineering

  • Informatics / Information network

  • Energy Engineering / Earth resource engineering, Energy sciences

  • Energy Engineering / Nuclear engineering

  • Frontier Technology (Aerospace Engineering, Marine and Maritime Engineering) / Marine engineering

Education

  • Tokyo Institute of Technology   Academy for Global Nuclear Safety and Security Agent, Leading Graduate School

    2017.6 - 2022.3

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  • Tokyo Institute of Technology   School of Environment and Society   Graduate Major in Nuclear Engineering, Department of Transdisciplinary Science and Engineering

    2019.4 - 2022.3

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    Country: Japan

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  • Tokyo Institute of Technology   School of Environment and Society   Graduate Major in Nuclear Engineering, Department of Transdisciplinary Science and Engineering

    2017.4 - 2019.3

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  • Kyushu Institute of Technology   School of Engineering   Department of Mechanical and Control Engineering

    2014.4 - 2017.3

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    Country: Japan

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  • Sasebo National College of Technology   Department of Mechanical Engineering

    2009.4 - 2014.3

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    Country: Japan

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Research History

  • Institute of Science Tokyo   Laboratory for Zero-Carbon Energy, Institute of Integrated Research   Specially Appointed Assistant Professor

    2024.10

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  • Tokyo Institute of Technology   Institute of Innovative Research   Specially Appointed Assistant Professor

    2024.1 - 2024.9

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  • Tokyo Institute of Technology   Institute of Innovative Research   Researcher

    2023.7 - 2023.12

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  • Hitachi, Ltd.,

    2022.4 - 2023.6

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  • 日本学術振興会特別研究員DC2

    2020.4 - 2022.4

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  • Tokyo Institute of Technology

    2019.4 - 2022.3

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Professional Memberships

  • Atomic Energy Society of Japan

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  • Institute of Nuclear Material Management (INMM) Japan Chapter

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  • The Japan Society of Naval Architects and Ocean Engineers

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  • Japan Society of Maintenology

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Committee Memberships

  • Atomi Energy Society of Japan   Committee member, Technical Committee for Technology of Nuclear Fuel Cycle Simulation for Nuclear Future Scenarios  

    2023.12 - 2025.11   

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    Committee type:Academic society

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  • OECD NEA   Expert Group on Advanced Fuel Cycle Scenarios (EGAFCS)  

    2023.11   

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    Committee type:Government

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  • 日本原子力学会 学生連絡会   副会長  

    2021.4 - 2022.3   

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  • Atomic Energy Society of Japan Student Network   Chairman  

    2020.4 - 2021.3   

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  • 日本原子力学会 原子力の未来像WG   委員  

    2020 - 2022   

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    Committee type:Academic society

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  • 日本原子力学会学生連絡会   副会長  

    2019.4 - 2020.3   

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    Committee type:Academic society

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Papers

  • Implementation of ideal cascade model for uranium enrichment to nuclear fuel cycle simulator

    Takumi Abe, Taiga Suzuki, Tomohiro Okamura, Masahiko Nakase

    Annals of Nuclear Energy   232   112224 - 112224   2026.7

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    Publishing type:Research paper (scientific journal)   Publisher:Elsevier BV  

    DOI: 10.1016/j.anucene.2026.112224

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  • Preliminary design and front-end fuel cycle assessment of 200 MWt marine molten chloride fast reactor

    Andika Putra Dwijayanto, Kenji Nishihara, Tomohiro Okamura, Masahiko Nakase

    Annals of Nuclear Energy   229   112124 - 112124   2026.5

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    Publishing type:Research paper (scientific journal)   Publisher:Elsevier BV  

    DOI: 10.1016/j.anucene.2026.112124

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  • Evaluation of Aluminum Hexacyanoferrate utilization for PGM and Mo removal from simulated high-level-raffinates in reprocessing for repository area minimization

    Masahiko Nakase, Ria Mishima, Takumi Abe, Tomohiro Okamura, Hidekazu Asano

    Annals of Nuclear Energy   224   111569 - 111569   2025.12

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    Publishing type:Research paper (scientific journal)   Publisher:Elsevier BV  

    DOI: 10.1016/j.anucene.2025.111569

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  • Analysis of the Necessity and Usefulness of MA Temporary Storage Technology for the Sustainable Nuclear Fuel Cycle Reviewed

    Tomohiro Okamura, Masahiko Nakase, Kenji Takeshita, Takashi Shimada, Yuki Konishi, Keisuke Nishimura, Hitomi Ishida, Tomoo Yamamura

    Progress in Nuclear Science and Technology   7 ( 2025 )   2025.2

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    Authorship:Lead author   Language:English   Publishing type:Research paper (scientific journal)  

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  • Cost-reduced depletion calculation including short half-life nuclides for nuclear fuel cycle simulation Reviewed

    Tomohiro Okamura, Ryota Katano, Akito Oizumi, Kenji Nishihara, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    Journal of Nuclear Science and Technology (Published online)   2022.10

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

    DOI: 10.1080/00223131.2022.2131646

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  • Optimization of waste management for mixed oxide fuel in light-water reactors: Evaluation of the effectiveness of blending spent uo2 and mixed oxide fuels in reprocessing

    Eriko Minari, Tomohiro Okamura, Hidekazu Asano, Masahiko Nakase, Kenji Takeshita

    ANNALS OF NUCLEAR ENERGY   169   2022.5

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

    DOI: 10.1016/j.anucene.2021.108926

    Web of Science

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  • Optimal waste loading in high-level nuclear waste glass from high-burnup spent fuel for waste volume and geological disposal footprint reduction

    Tomofumi Sakuragi, Tomohiro Okamura, Ryo Hamada, Hidekazu Asano, Eriko Minari, Masahiko Nakase, Kenji Takeshita, Toshiro Oniki, Midori Uchiyama

    MRS ADVANCES   7 ( 7-8 )   150 - 154   2022.3

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

    DOI: 10.1557/s43580-022-00232-3

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  • NMB4.0: development of integrated nuclear fuel cycle simulator from the front to back-end Reviewed

    Tomohiro Okamura, Ryota Katano, Akito Oizumi, Kenji Nishihara, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    EPJ Nuclear Sci. Technol.   7 ( 19 )   2021.11

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  • Evaluation of the technical options of radioactive waste management for utilization of MOX fuel: thermal impact of minor actinide separation with geological disposal of high-level waste Reviewed

    Eriko Minari, Tomohiro Okamura, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    Journal of Nuclear Science and Technology   1 - 11   2021.6

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

    DOI: 10.1080/00223131.2021.1918590

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  • Study on nuclear fuel cycle with less-impact radioactive waste management -Impact of Cs and Sr separation on reducing the geological disposal area

    Masahiko Nakase, Tomohiro Okamura, Eriko Minari, Hidekazu Asano, KENJI TAKESHITA

    Bull. Lab. Adv. Nucl. Energy   2020.3

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  • Reduction of the Waste Occupied Area by Nuclide Separation and Horizontal Emplacement of Waste Package Reviewed

    T. Okamura, E. Minari, M. Nakase, H.Asano, K. Takeshita

    WM SYMPOSIA   2020.3

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  • 使用済燃料対策のIAEA国際会議(教訓を活かす) ―傾向分析と最優秀若手研究者賞受賞―

    岡村知拓

    原子力学会誌「アトモス」   2020.2

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    Language:Japanese  

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  • Interrelationships and the effects of introducing separation technologies in the nuclear fuel cycle for enhanced radioactive waste management

    Tomohiro Okamura, Eriko Minari, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference   622 - 628   2020

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    Publishing type:Research paper (international conference proceedings)  

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  • Interrelationship between effect of introducing separation technologies and conditions of nuclear fuel cycle for less-impacted radioactive waste management Reviewed

    T. Okamura, E. Minari, M. Nakase, H.Asano, K. Takeshita

    GLOBAL2019   2019.9

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  • Enviromental load reduction of geological repository by minor actinide separation: Utilization of MOX fuel in future fuel cycle system Reviewed

    Eriko Minari, Tomohiro Okamura, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, IAEA, Vienna, Austria   2019.4

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  • Reduction of geological disposal area by introducing partitioning technologies under conditions of high burn-up operation and high content vitrified waste Reviewed

    Tomohiro Okamura, Eriko Minari, Masahiko Nakase, Hidekazu Asano, Kenji Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, IAEA, Vienna, Austria   2019.4

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  • Cross-sectional study on nuclear energy system for less-impacted radioactive waste management - Effect of the various spent nuclear fuel properties and reprocessing conditions on the geological disposal Reviewed

    Hidekazu Asano, Tomohiro Okamura, Eriko Minari, Masahiko Nakase, Kenji Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, IAEA, Vienna, Austria   2019.4

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  • Effective use of 234U in Throium fuel cycle Reviewed

    Masahiko Nakase, Eriko Minari, Tomohiro Okamura, Hiroshi Sagara, Masaki Saito, Kenji Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, IAEA, Vienna, Austria   2019.4

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  • Effect of Cs and Sr separation on occupied area reduction in current nuclear energy system and its evaluation by CAERA index Reviewed

    Tomohiro Okamura, Kota Kawai, Eriko Minari, Hidekazu Asano, Masahiko Nakase, KENJI TAKESHITA

    Seper Sci Technol   2018.12

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    Separation of Cs and Sr from high-level liquid waste (HLLW) contributes to reducing heat generation and correspondingly to minimizing the required use of space in geological disposal repositories for high-level radioactive waste. To maximize the impact of Cs and Sr separation on reducing the occupied area of a repository, it is necessary to consider both the front-end and back-end stages of the nuclear energy system. Therefore, we quantitatively surveyed factors that potentially affect the reduction in the occupied area – that is, the area required for disposal of one waste package – when introducing Cs and Sr separation. From an evaluation using the Comprehensive Analysis of Effects on Reduction of Disposal Area (CAERA) index, we found that in case of a 15-year cooling period of spent nuclear fuel (SNF) after discharge, which is the current operational condition at the Rokkasho Reprocessing Plant, a maximum reduction of 30% in occupied area was achieved for 25 and 30 wt% waste-loaded vitrified waste with Cs and Sr separation. In that case, separation of more than 70% of Cs and Sr was required based on the current reference case for the Japanese geological disposal concept (the so-called H12 Report). In addition, the effectiveness of Cs and Sr separation for reducing the occupied area was drastically decreased if the cooling period after discharge was extended beyond 15 years; for instance, vitrified waste with a more than 40-year cooling period showed almost no reduction in occupied area. This was because the amount of 241Am, which is generated from the beta decay of 241Pu, and the contribution of 241Am to heat generation in vitrified waste increased as the cooling period became longer. The results suggested that the cooling period of the SNF, the waste loading of the vitrified waste, the Cs and Sr separation ratio and the occupied area of the waste were key factors governing the effectiveness of Cs and Sr separation for geological disposal area reductions.

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  • Cross-sectional study on nuclear fuel cycle for less-impacted radioactive waste management and disposal Reviewed

    Tomohiro Okamura, Masahiko Nakase, Kota Kawai, Eriko Minari, Hidekazu Asano, KENJI TAKESHITA

    Bull. Lab. Adv. Nucl. Energy   2018

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Books

  • 原子力の門戸開放!今こそ原子力オンライン学習プラットフォームの構築を!

    岡村知拓

    原子力の新潮流vol.1-1  2020.8 

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  • 使用済燃料対策のIAEA国際会議(教訓を活かす)-傾向分析と最優秀若手研究者賞受賞-

    三枝利有, 岡村知拓, 朝野英一( Role: Joint author)

    日本原子力学会誌ATOMOΣVol.62  2020.2 

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  • 特集「五輪への想い」日本社会が世界のトップアスリートであるために

    岡村知拓

    エネルギーレビューvol.474 2020年7月号 

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MISC

  • Development of an exploration scheme of chelate reagents for targeted alpha therapy by transfer learning

    中瀬正彦, 西原尚宏, 岡村知拓, IKHWAN Fauzia Hanum, 白崎謙次, 宮脇琢斗, 松井孝太

    日本イオン交換研究発表会講演要旨集   36th   2023

  • Selection of nuclides for mass-balance analysis of fission products

    Tomohiro Okamura, Akito Oizumi, Kenji Nishihara, Masahiko Nakase, Kenji Takeshita

    JAEA-Data/Code   ( 2020-023 )   2021.3

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    J-GLOBAL

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  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal (18) Effects of UO2-MOX blended vitrified waste disposal on reduction of environmental impact

    三成映理子, 岡村知拓, 中瀬正彦, 桜木智史, 浜田涼, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2021   2021

  • Development of Accelerated Exponential Method for Burnup Calculation in Nuclear Material Balance Code

    岡村知拓, 大泉昭人, 西原健司, 中瀬正彦, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2021   2021

  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal, (17) Study on the reduction of footprint of geological repository by combination of time factors in backend process and waste emplacements at geological repository

    岡村知拓, 三成映理子, 中瀬正彦, 桜木智史, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会秋の大会予稿集(CD-ROM)   2020   2020

  • Basic research programs of vitrification technology for waste volume reduction (79) Scenario study on the volume reduction and disposal impact of waste generated from high-burnup UO2 fuel

    桜木智史, 朝野英一, 朝野英一, 岡村知拓, 三成映理子, 中瀬正彦, 竹下健二, 鬼木俊郎

    日本原子力学会秋の大会予稿集(CD-ROM)   2020   2020

  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal (13) Waste management issues arising from Pu burning in LWR

    桜木智史, 朝野英一, 朝野英一, 岡村知拓, 三成映理子, 中瀬正彦, 竹下健二, 稲垣八穂広, 新堀雄一, 佐藤正知

    日本原子力学会春の年会予稿集(CD-ROM)   2020   2020

  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal (15) Study on setting a standard case of the MOX vitrified waste disposal and the effect of MA separation to the thermal property

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2020   2020

  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal, (14) Thermal property of spent MOX fuel and its effect on geological disposal

    岡村知拓, 三成映理子, 川合康太, 中瀬正彦, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2020   2020

  • Technical options of radioactive waste management for the second half of the 21st Century, in consideration of Pu utilization and less environmentally impacted geological disposal, (16) Load evaluation of geological disposal for MOX fuel-derived wastes

    朝野英一, 朝野英一, 桜木智史, 三成映理子, 岡村知拓, 中瀬正彦, 竹下健二, 稲垣八穂広, 新堀雄一, 佐藤正知

    日本原子力学会春の年会予稿集(CD-ROM)   2020   2020

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(10)横置き方式による廃棄体専有面積削減効果の検討

    岡村知拓, 三成映理子, 中瀬正彦, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2019   2019

  • 高レベル放射性廃液ガラス固化体の高品質・減容化のための白金族元素高収着能を有するシアノ基架橋型配位高分子材料の開発(4)プロセス評価

    竹下健二, 岡村知拓, 針貝美樹, 稲葉優介, 中瀬正彦, 渡邊真太, 尾上順

    日本原子力学会春の年会予稿集(CD-ROM)   2019   2019

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(9)ガラス固化プロセスにおける廃棄物含有率と処分場の負荷低減

    朝野英一, 朝野英一, 川久保政洋, 岡村知拓, 三成映理子, 中瀬正彦, 竹下健二, 稲垣八穂広, 新堀雄一, 佐藤正知

    日本原子力学会春の年会予稿集(CD-ROM)   2019   2019

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(11)MOX燃料におけるMA分離と処分場負荷削減効果の検討

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2019   2019

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(3)核燃料サイクル諸条件が使用済燃料とガラス固化体に及ぼす影響

    川合康太, 岡村知拓, 三成映理子, 川久保政洋, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2018   2018

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(5)UO2使用済燃料冷却期間長期化におけるMA分離の効果

    三成映理子, 川合康太, 岡村知拓, 川久保政洋, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2018   2018

  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(4)Cs/Sr分離による高含有ガラス固化体処分の廃棄体専有面積評価

    岡村知拓, 川合康太, 三成映理子, 朝野英一, 朝野英一, 竹下健二

    日本原子力学会春の年会予稿集(CD-ROM)   2018   2018

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Presentations

  • RISTEX Project: Towards Integrating Diverse Expertise and Public Preferences in Nuclear Policy (2) Public and Expert Preferences for Nuclear Fuel Cycle in Japan: Insights from Conjoint Experiments

    Yuji Fukaya, Reona Hayashi, Syunsaku Komatsuzaki, Hirofumi Miwa, So Morikawa, Kenji Nishihara, Tomohiro Okamura

    TWoFCS2026 (The 7th Technical Workshop on Fuel Cycle Simulation 2026)  2026.4 

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    Event date: 2026.4

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Japan, Tokyo  

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  • RISTEX Project: Towards Integrating Diverse Expertise aro Public Preferences in Nuclear Policy: (3) Talking with Al: Experimental Evidence on the Effects of Al Discourse on Public Attitude Formation toward HLW Disposal Facility Siting Policy

    Hidekazu Asano, Yuji Fukaya, Reona Hayashi, Syunsaku Komatsuzaki, Yuji Matsuo, Hirofumi Miwa, So Morikawa, Kenji Nishihara, Tomohiro Okamura, Tomoya Yokoyama

    TWoFCS2026 (The 7th Technical Workshop on Fuel Cycle Simulation 2026)  2026.4 

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    Event date: 2026.4

    Language:English   Presentation type:Poster presentation  

    Venue:Japan, Tokyo  

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  • Visualizing, Changing, and Deepening Public Preferences in Nuclear Policy: An Integrative Study Based on Public-Expert Comparison, Information Interventions, and AI-Facilitated Dialogue02_Talking with AI: Experimental Evidence on the Effects of AI Discourse on Public Attitude Formation toward HLW Disposal Facility Siting Policy

    Hidekazu Asano, Yuji Fukaya, Reona Hayashi, Syunsaku Komatsuzaki, Yuji Matsuo, Hirofumi Miwa, So Morikawa, Kenji Nishihara, Tomohiro Okamura, Tomoya Yokoyama

    Atomic Energy Society of Japan 2026 Spring Annual Meeting  2026.3 

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    Event date: 2026.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Japan, Kumamoto  

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  • Impacts of re-enrichment of reprocessed uranium on the stable supply of nuclear fuel

    Kenji Takeshita, Tomohiro Okamura

    Atomic Energy Society of Japan 2026 Spring Annual Meeting  2026.3 

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    Event date: 2026.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Japan, Kumamoto  

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  • Study on a Roadmap for Nuclear-Powered Ships Towards 2050 GHG Net-Zero

    Tomohiro Okamura, Akira Tatsumi, Kenji Nishihara, Riku Morigaki, Katsunori Sakaguchi, Hidekazu Asano, Tomonori Ihara, Tadafumi Koyama, Jun Kato

    2020 Japan Society of Naval Architects and Ocean Engineers Autumn Lecture  2025.11 

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    Event date: 2025.11

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Japan, Himeji  

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  • ガウス過程を活用した異常検知技術の開発

    Tomohiro Okamura

    AI Maintenance Society Generative AI Academia First Results Report Session  2025.10 

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    Event date: 2025.10

    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Tomoo Yamamura, Takashi Shimada, Tomohiro Okamura, Masahiko Nakase, Kenji Takeshita, Hirotaka Konishi, Keisuke Nishimura, Taisuke Tsukamoto, Hitomi Ishida, Yasutoshi Ban

    Atomic Energy Society of Japan 2024 Autumn Meeting  2024.9 

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    Event date: 2024.9

    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Taiga Suzuki, Tomohiro Okamura, Masahiko Nakase, Kenji Nishihara, Takumi Abe

    Atomic Energy Society of Japan 2024 Autumn Meeting  2024.9 

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    Event date: 2024.9

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  • Kenji Takeshita, Tomohiro Okamura, Masahiko Nakase

    Atomic Energy Society of Japan 2024 Autumn Meeting  2024.9 

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  • Tomohiro Okamura

    Atomic Energy Society of Japan 2024 Autumn Meeting  2024.9 

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  • Tomohiro Okamura, Masahiko Nakase, Kenji Takeshita, Takashi Shimada, Hirotaka Konishi, Keisuke Nishimura, Hitomi Ishida, Tomoo Yamamura

    Atomic Energy Society of Japan 2024 Autumn Meeting  2024.9 

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    Event date: 2024.9

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  • [keynote speech] Digital Twin Project for Innovative Nuclear Energy System-Application to Radioactive Waste Management-

    Tomohiro Okamura, Takahiro Nishihara, Masahiko Nakase

    Organized by OECD NEA:Working Party on Information, Data, and Knowledge Management (WP-IDKM) general meeting  2024.2 

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    Event date: 2024.2

    Language:English   Presentation type:Symposium, workshop panel (nominated)  

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  • Reduction of the Waste Occupied Area by Nuclide Separation and Horizontal Emplacement of Waste Package

    T. Okamura, E. Minari, M. Nakase, H.Asano, K. Takeshita

    WM SYMPOSIA2020  2020.3 

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  • Impact of Combination of Partitioning and Horizontal Emplacement of Waste Package on Foot-print of Geological Repository

    T. Okamura, E. Minari, M. Nakase, H.Asano, K. Takeshita

    WM SYMPOSIA2020  2020.3 

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  • Interrelationship between effect of introducing separation technologies and conditions of nuclear fuel cycle for less-impacted radioactive waste management

    T. Okamura, E. Minari, M. Nakase, H.Asano, K. Takeshita

    Global2019  2019.9 

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  • Evaluation of the technical options on waste management and disposal: Future investigation on environmental impact analysis where the MA separation and nuclide migration is correlated

    E. Minari, T. Okamura, M. Nakase, H. Asano, T. Ohnuki, K. Takeshita

    Migration2019 

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  • Reduction of geological disposal area by introducing partitioning technologies under conditions of high burn-up fuel and high content vitrified waste Invited

    T. Okamura, E. Minari, M. Nakase, H. Asano, K. Takeshit

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors (SFM) 2019  2019.6 

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    Event date: 2019.6

    Language:English   Presentation type:Oral presentation (invited, special)  

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  • Cross-sectoral study on nuclear energy system for less-impacted geological disposal of high-level radioactive waste in consideration of variation of spent nuclear fuel and technical feasibility of reprocessing and vitrification processes

    H. Asano, T. Okamura, E. Minari, M. Nakase, K. Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors 2019  2019.6 

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  • Effective use of U-234 in Th fuel cycle

    M. Nakase, E. Minari, T. Okamura, H. Asano, K. Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors 2019 

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    Event date: 2019.6

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  • Reduction of geological disposal area by introducing partitioning technologies under conditions of high burn-up fuel and high content vitrified waste

    T. Okamura, E. Minari, M. Nakase, H. Asano, K. Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors 2019  2019.6 

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  • Effect of Cs and Sr separations on occupied area reduction in current nuclear energy system and its evaluation by CAERA index

    T. Okamura, K. Kawai, E. Minari, M. Nakase, H.Asano, K. Takeshita

    20th Symposium on Separation Science and Technology for Energy applications  2018.10 

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  • 環境負荷低減型地層処分に向けた多様な燃料サイクルシナリオ~UO2燃料とMOX燃料におけるMA分離と処分場負荷削減効果の検討~

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会2019年春の年会 学生ポスターセッション  2019.3 

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  • 多様な核燃料サイクルシナリオにおける分野横断型研究 多様な核燃料サイクルシナリオにおける分野横断型研究 ~Cs・Sr分離およびガラス固化体貯蔵期間の地層処場面積に与える影響~

    岡村知拓, 三成映理子, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会2019年春の年会 学生ポスターセッション  2019.3 

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  • 環境負荷低減型地層処分に向けた多様な燃料サイクルシナリオ~MOX燃料におけるMA分離と処分場負荷削減効果の検討~

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会第12回学生研究発表会-原子力・放射線分野-  2019.3 

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  • 高レベル放射性廃液ガラス固化体の高品質・減容化のための白金族元素高収着能を有するシアノ基架橋型配位高分子材料の開発(4) プロセス評価

    竹下健二, 岡村知拓, 針貝美樹, 稲葉優介, 中瀬正彦, 渡邊 真太, 尾上順

    日本原子力学会2019年春の年会  2019.3 

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  • 21 世紀後半に向けた廃棄物管理の選択肢:Pu 利用推進と環境負荷低減型地層処分 に関する研究(9)ガラス固化プロセスにおける廃棄物含有率と処分場の負荷低減

    朝野英一, 川久保政洋, 岡村知拓, 三成映理子, 中瀬正彦, 竹下健二, 稲垣 八穂広, 新堀 雄一, 佐藤 正知

    日本原子力学会2019年春の年会  2019.3 

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  • 多様な核燃料サイクルシナリオにおける分野横断型研究 ~Cs・Sr分離および廃棄体横置き方式導入による地層処分場面積削減効果の検討~

    岡村知拓, 三成映理子, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会「第14回再処理・リサイクル部会セミナー」  2018.12 

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  • 21 世紀後半に向けた廃棄物管理の選択肢:Pu 利用推進と環境負荷低減型地層処分に関する研究 (11) MOX 燃料における MA 分離と処分場負荷削減効果の検討

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会2019年春の年会  2019.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (14)使用済MOX燃料の発熱特性と地層処分場の温度特性への影響

    岡村 知拓, 三成 映理子, 川合 康太, 中瀬 正彦, 朝野 英一, 竹下 健二

    日本原子力学会2020年春の年会  2020.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(13)軽水炉によるPu利用における廃棄物処理処分の課題

    桜木 智史, 朝野 英一, 三成 映理子, 岡村 知拓, 中瀬 正彦, 竹下 健二, 稲垣 八穂広, 新堀 雄一, 佐藤 正知

    日本原子力学会2020年春の年会  2020.3 

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  • 学生連絡会六ケ所原子力施設見学会の活動報告

    福田 貴斉, 岡村 知拓, 大杉 遥, 左藤 維摩, 村本 武司

    日本原子力学会「第15回再処理・リサイクル部会セミナー」  2019.12 

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  • 多様なバックエンドシナリオのための諸量計算コードの開発~FP核種の拡張とNMBコード用核データライブラリ作成ツールの開発~

    岡村 知拓, 大泉 昭人, 三成 映理子, 中瀬 正彦, 朝野 英一, 西原健司, 竹下 健二

    日本原子力学会「第15回再処理・リサイクル部会セミナー」  2019.12 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(16)MOX燃料を利用する原子力システムにおける廃棄物の負荷評価

    朝野 英一, 桜木 智史, 三成 映理子, 岡村 知拓, 中瀬 正彦, 竹下 健二, 稲垣 八穂広, 新堀 雄一, 佐藤 正知

    日本原子力学会2020年春の年会  2020.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (15)MOX使用済燃料由来ガラス固化体処分におけるMA分離効果と発熱特性を考慮した標準ケースの検討

    三成 映理子, 岡村 知拓, 中瀬 正彦, 朝野 英一, 竹下 健二

    日本原子力学会2020春の年会  2020.3 

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  • 廃棄体定置横置き方式による処分場面積削減効果の検討

    岡村知拓, 三成映理子, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会第12回学生研究発表会-原子力・放射線分野-  2019.3 

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  • MOX燃料利用における廃棄物量と処分面積削減のための処分方法最適化の検討

    三成映理子, 岡村知拓, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会2021年春の年会 学生ポスターセッション  2021.3 

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  • PARC-MAを用いたMA簡素化分離プロセス検討に基づく環境負荷低減型地層処分に関する研究

    重清直也, 中瀬正彦, 岡村知拓, 三成映理子, 朝野英一, 竹下健二, 津幡靖宏, 伴康俊, 松村達郎

    日本原子力学会2021年春の年会 学生ポスターセッション  2021.3 

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  • NMBコードの燃焼計算に用いる高速行列指数法の開発

    岡村 知拓, 西原 健司, 大泉 昭人, 中瀬 正彦, 竹下 健二

    日本原子力学会2021年春の年会  2021.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (18)UO2-MOX混合ガラス固化体による処分負荷低減に関する研究

    三成 映理子, 岡村 知拓, 中瀬 正彦, 桜木 智史, 浜田 涼, 朝野 英一, 竹下 健二

    日本原子力学会2021年春の年会  2021.3 

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  • 放射性廃棄物の減容化に向けたガラス固化技術の基盤研究(79)高燃焼度UO2燃料から発生する廃棄物の減容及び地層処分の負荷影響に関するシナリオ評価

    桜木 智史, 朝野 英一, 岡村 知拓, 三成 映理子, 中瀬 正彦, 竹下 健二, 鬼木 俊郎

    日本原子力学会2020年秋の大会  2020.9 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (17) 処分場面積削減に対するバックエンドプロセスの時間因子と廃棄体定置方式の組合せに関する研究

    岡村 知拓, 三成 映理子, 中瀬 正彦, 桜木 智史, 朝野 英一, 竹下 健二

    日本原子力学会2020年秋の大会  2020.9 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (4)Cs/Sr分離による高含有ガラス固化体処分の廃棄体専有面積評価

    岡村知拓, 川合康太, 三成映理子, 朝野英一, 竹下健二

    日本原子力学会2018年春の年会  2018.3 

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  • WEB方式による対話会に関するパネルディスカッション

    金氏 顕, 中村 秀夫, 渡邊 政幸, 松永 一郎, 大野 崇, 岡村 知拓

    日本原子力学会2021年春の年会  2021.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (3)核燃料サイクル諸条件が使用済燃料とガラス固化体に及ぼす影響

    川合康太, 岡村知拓, 三成映理子, 川久保政洋, 朝野英一, 竹下健二

    日本原子力学会2018年春の年会  2018.3 

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  • Cs/Sr分離による高含有ガラス固化体処分の廃棄体専有面積評価

    岡村知拓, 川合康太, 三成映理子, 朝野英一, 竹下健二

    日本原子力学会2018年春の年会 学生ポスターセッション  2018.3 

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  • Comprehensive study on nuclear fuel cycle toward sophisticated system; connecting from electric generation to final geological disposal

    M. Nakase, T. Okamura, E. Minari, K. Kawai, H. Asano, K. TAKESHITA

    2018 

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  • 多様な燃料サイクルシナリオにおける地層処分面積削減効果指標の検討~MA 分離の MOX 使用済燃料ガラス固化体処分に対する有効性~

    三成映理子, 川合康太, 岡村知拓, 朝野英一, 竹下健二

    日本原子力学会「第13回再処理・リサイクル部会セミナー」  2017.12 

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  • 多様な燃料サイクルシナリオにおける地層処分面積削減効果指標の検討~Cs/Sr分離による高含有ガラス固化体処分の妥当性評価~

    岡村知拓, 三成映理子, 川合康太, 朝野英一, 竹下健二

    日本原子力学会「第13回再処理・リサイクル部会セミナー」  2017.12 

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  • Environmental Load Reduction of Geological Repository by Minor Actinide Separation; Utilization of MOX Fuel in Future Fuel Cycle System

    E. Minari, T. Okamura, M. Nakase, H. Asano, K. Takeshita

    International Conference on the Management of Spent Fuel from Nuclear Power Reactors (SFM) 2019 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (6)処分場負荷低減を目指したバックエンドシステムの研究開発への提言

    竹下健二, 川合康太, 岡村知拓, 三成映理子, 川久保政洋, 坪能和宏, 朝野英一, 千葉豪, 稲垣八穂広, 新堀雄一

    日本原子力学会2018年春の年会  2018.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究 (5)UO2使用済燃料冷却期間長期化におけるMA分離の効果

    三成映理子, 川合康太, 岡村知拓, 川久保政洋, 朝野英一, 竹下健二

    日本原子力学会2018年春の年会  2018.3 

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  • 日本原子力学会学生連絡会の紹介

    岡村知拓

    「VISION2050 - 事故を振り返り未来を見据える」-原子力の未来像を考える-  2021.3 

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  • 21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(10)横置き方式による廃棄体専有面積削減効果の検討

    岡村知拓, 三成映理子, 中瀬正彦, 朝野英一, 竹下健二

    日本原子力学会2019年春の年会  2019.3 

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Awards

  • 核友会賞

    2022.3   東工大核友会  

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  • 優秀講演賞

    2022.3   日本原子力学会 原子力安全部会  

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  • 2021年日本原子力学会秋の大会 学生ポスターセッション 最優秀賞

    2021.9   日本原子力学会   NMB4.0: 統合的な核燃料サイクルシミュレーションコードの開発

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  • 優秀講演賞

    2021.3   日本原子力学会バックエンド部会  

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  • Award of Excellence

    2020.2   The Nuclear Waste Management Organization of Japan   The 1st Proposal Contest for Nuclear Waste disposal

    Tomohiro Okamura

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  • Excellence of presentation award

    2019.12   15th conference on The Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan

    Tomohiro Okamura

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  • Winner of Winners

    2019.6   IAEA (International Atomic Energy Agency)   Young Generation Event Spent Fuel Management Challenge

    Tomohiro Okamura

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    Award type:Award from international society, conference, symposium, etc.  Country:Austria

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  • Student Excellence Award

    2019.3   Graduate Major of Nuclear Engineering, Tokyo Institute of Technology  

    Tomohiro Okamura

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  • New face award

    2018.3   student poster session, 2018 Annual Meeting of Atomic Energy Society of Japan

    Okamura Tomohiro

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  • Best presentation award

    2017.12   13th conference on The Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan

    Tomohiro Okamura

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Research Projects

  • Study of nuclear energy system with the reduced radioactive waste disposal by molten salt reactor

    Grant number:20J14956  2020.4 - 2022.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research Grant-in-Aid for JSPS Fellows  Grant-in-Aid for JSPS Fellows

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    Grant amount:\2100000 ( Direct Cost: \2100000 )

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Other

  • NMBコードの無償公開

    2022.3

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    博士後期課程で開発した核燃料サイクルシミュレーターNMB4.0 (Nuclear Material Balance analysis code version 4.0)を無償公開した。https://nmb-code.jp/

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Media Coverage

  • 停滞する高レベル放射性廃棄物処分事業に提言安全標語「2μSv/年」で地層処分の安全性を伝えたい Newspaper, magazine

    東方通信社  月間コロンブス  2020.8

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