Updated on 2025/11/22

写真a

 
SAGARA HIROSHI
 
Organization
Institute of Integrated Research Laboratory for Zero-Carbon Energy Professor
Title
Professor
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Degree

  • Doctor of Engineering ( 2005.3   Tokyo Institute of Technology )

  • Master (Engineering) ( 2002.3   Tokyo Institute of Technology )

Research Interests

  • Non-proliferation Nuclear Reactor and Nuclear Energy Sysmte Engineering Multi Physics Analysis on Complex Event Partitioning and Transmutation Non-destructive Assay Technology Disaster Prevention and Resilience

  • Zero-release of High Level Nuclear Waste Partitioning and Transmutation of Nuclear Waste Neutronics Proliferation Resisatance of Nuclear System

  • Nuclear Safety

  • Security

  • 放射性廃棄物のゼロリリース 放射性廃棄物の郡分離・核変換 中性子工学 核拡散抵抗性

Research Areas

  • Energy Engineering / Nuclear engineering

Education

  • Tokyo Institute of Technology   Graduate School, Division of Science and Engineering   Department of Nuclear Engineering

    - 2005.3

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    Notes: Doctor later Completed

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  • Tokyo Institute of Technology   Science of Engineering   Nuclear Engineering

    - 2005

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    Country: Japan

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  • Tokyo Institute of Technology   Graduate School, Division of Science and Engineering   Department of Nuclear Engineering

    - 2002.3

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    Notes: Master course Completed

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  • Tokyo Institute of Technology   Faculty of Science   Department of Applied Physics

    - 1999.3

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    Notes: Graduated

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  • Tokyo Institute of Technology   School of Science   Department of Applied Physics

    1995.4 - 1999.3

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Research History

  • Institute of Science Tokyo   Institute of Innovative Reseach   Professor   Dr.

    2024.10

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    Country:Japan

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  • Tokyo Institute of Technology   Institute of Innovative Research   Professor

    2024.4 - 2024.9

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    Country:Japan

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  • Tokyo Institute of Technology   Institute of Innovative Research   Associate Professor

    2016.4

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  • Tokyo Institute of Technology   Institute of Innovative Research   Associate Professor

    2014.3 - 2024.3

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    Country:Japan

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  • Tokyo Institute of Technology   Research Laboratory for Nuclear Reactors   Associate Professor

    2014.3 - 2016.3

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  • Japan Atomic Energy Agency   Integreted Support Center of Nuclear Non-proliferation and Nuclear Security   Senior Post-doctral Fellow

    2011.4 - 2013.3

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  • Idaho National Laboratory   Nuclear Fuels and Materials Division, Nuclear Science & Technology   Visiting Scientist

    2008.10 - 2009.10

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  • Tokyo Institute of Technology   Research Laboratory for Nuclear Reactor   Assistant Professor

    2007.4 - 2014.2

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  • Tokyo Institute of Technology   Research Laboratory for Nuclear Reactors, System and Safety Engineering   Assistant Professor

    2007.4 - 2014.2

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  • Tokyo Institute of Technology   Research Laboratory for Nuclear Reactors / System and Safety Engineering   Assistant Professor

    2005.4 - 2007.3

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  • International Atomic Energy Agency   Nuclear Fuel Cycle & Waste, Department of Energy   Intern

    2004.1 - 2004.3

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  • Tokyo Institute of Technology   Research Laboratory for Nuclear Engineering   Research Assistant

    2003 - 2005

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  • University of California Berkeley, USA   Department of Nuclear Engineering   Visiting Scholar

    2000.6 - 2001.3

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Professional Memberships

Papers

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Books

  • 原子力で遊ぼう-東工大生による原子力ゲームコンテスト優秀作品集-

    COE-INES Research Assistant, COE-INES(原子力で遊ぼう-東工大生による原子力ゲームコンテスト優秀作品集-)

    2008.3 

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    Language:Japanese   Book type:Scholarly book

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MISC

  • Survey Research on Feasibility and 3S Characteristics of Off-grid Next-generation Small Reactors Satisfying Demand of Energy and Green Transformation in Industry Sector

    武智希実, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Vital Areas Identification Evaluation of Sodium Cooled Fast Reactors with New Threat Definition

    石井孝仁, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Performance analysis of large scale LWRs loaded with uranium-silicide fuels for enhancement of nuclear safety and security features

    森悠輔, 相楽洋, CHONG Hong Fatt

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Safeguards by design of sodium-cooled fast reactor with online re-fueling function

    寺山正太郎, 相楽洋, LISOWSKI Eva

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Enhancement of Core Lifetime and Safety Performance of Reduced-Moderation Water Reactors with Accident Tolerant HALEU Fuel-Research Plan-

    日下雄都, 相楽洋, CHONG Hong Fatt, 森悠輔

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Estimating the origin of reprocessed Pu for Nuclear Forensics (2) Identification of Key Signature Nuclides

    佐藤颯, 相楽洋, HAN Chi Young, 木村祥紀, 田辺鴻典

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Applicability of passive neutron non-destructive assay technique for Pu quantification in advanced fast fuels

    江口綾, 相楽洋, 三星夏海, 長谷竹晃

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • The Program of NRA Human Resource Development “Advanced Nuclear 3S Education and Training in Cyber-Physical Space (ANSET-CP)′′ (3) FY2024 Implementation Status

    HAN Chi Young, 相楽洋, 松本義久, 林崎規託, 塚原剛彦, 池上雅子, 片渕竜也, 木倉宏成, 鷹尾康一朗, 吉田克己, 高須大輝, 松浦知史

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Development of a Detection Technique for Nuclear Materials Using the Proton-Lithium Nuclear Reaction as a Photon Source

    片渕竜也, 國友理紗, 相楽洋, KIATKONGKAEW Krittanai, 石塚知香子, 田辺鴻典

    日本核物質管理学会年次大会論文集(Web)   45th   2024

  • Misuse Scenario Analysis of Accelerator-Driven System and the Effects of Dual C/S and Design Information Verification

    大泉昭人, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • The Program of NRA Human Resource Development “Advanced Nuclear 3S Education and Training in Cyber-Physical Space (ANSET-CP)” (2) FY2023 Implementation Status

    HAN Chi Young, 相楽洋, 松本義久, 林崎規託, 塚原剛彦, 池上雅子, 片渕竜也, 木倉宏成, 鷹尾康一朗, 吉田克己, 高須大輝, 松浦知史

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • Feasibility on Offshore Floating Nuclear Power Plant in terms of 3S characteristics (2) Vital area identification and path analysis

    原大輔, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • Damaging Mechanism of Reinforced Concrete Structure by Hypervelocity Projectile Impact-Effects on the Performance of Physical Protection System and Structural Safety-

    井上週, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • Development of a passive reactor shutdown device to prevent core damage accidents in fast reactors-Feasbility Study on Extended Specifications of the Devices and its Nonproliferation Features-

    川島正俊, 相楽洋, 守田幸路

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • Estimating the origin of reprocessed Pu for Nuclear Forensics (1) Research Plan

    佐藤颯, 相楽洋, 田辺鴻典

    日本核物質管理学会年次大会論文集(Web)   44th   2023

  • Feasibility of muon tomography to monitoring reactors without refueling (1) Research plan

    江口綾, 三星夏海, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Study on americium detection method based on photonuclear reactions

    田辺鴻典, 田辺鴻典, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Development of a method for the determination of plutonium in fuel debris by dual times neutron measurements

    長谷竹晃, 長谷竹晃, 相楽洋, 小菅義広, 中岫翔, 能見貴佳, 奥村啓介

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Nuclear Regulation Human Resource Development Program “The Advanced Nuclear 3S Education and Training in Cyber-Physical space” (1) Overview and Planning

    松本義久, 相楽洋, 千葉敏, 林崎規託, 塚原剛彦, 池上雅子, 片渕竜也, 木倉宏成, 鷹尾康一朗, 高須大輝, 吉田克己, 松浦知史

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Non-proliferation Features in Partitioning and Transmutation Cycle using Accelerator-driven System (3) Safeguards by Design by using Material Attractiveness Evaluation for TRU fuel cycle

    大泉昭人, 大泉昭人, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Development of a passive reactor shutdown device to prevent core damage accidents in fast reactors-Feasibility Study on Major Specification of the Devices and its Non-proliferation Features-

    川島正俊, 相楽洋, 守田幸路

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Feasibility on Offshore Floating Nuclear Power Plant in terms of 3S characteristics (1) Overview of Nuclear Security

    原大輔, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Study of Nuclear Material Detection Using a Portable Active Neutron Method Device

    田辺鴻典, 田辺鴻典, 米田政夫, 藤暢輔, 土屋兼一, 秋葉教充, 角田英俊, 相楽洋

    応用物理学会秋季学術講演会講演予稿集(CD-ROM)   83rd   2022

  • Damaging mechanism of structural materials by hypervelocity projectile impact (1) Damaging mechanism of reinforced concrete

    井上週, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Feasibility study on innovative small and medium modular light water reactor with inherent nuclear safety, security, and non-proliferation features (3) Evaluation for Proliferation Resistance

    三星夏海, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   43rd   2022

  • Proposal of neptunium-237 detection method based on photonuclear reaction

    田辺鴻典, 田辺鴻典, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Non-Destructive Assay Technology Using Passive Neutron Emission Tomography-Inhibiting Factor Sensitivity of Tomography Image-

    土屋克嘉, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Non-proliferation Features in Partitioning and Transmutation Cycle using Accelerator-driven System (2) Evaluation of Material Attractiveness of Uranium in ADS Fuel Assembly

    大泉昭人, 大泉昭人, 菅原隆徳, 相楽洋, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Improving nuclear safety and security performance of small and medium scale fast reactors by a passive reactor shutdown device (1) Research Plan

    岡崎陽香, 三星夏海, 川島正俊, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Nuclear Forensics Signatures of Spent Nuclear Fuel from Light Water Reactors

    加賀山雄一, 相楽洋, HAN Chi Young, 木村祥紀

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Feasibility study on innovative small and medium modular reactor with inherent nuclear safety, security, and non-proliferation features (2) Assessment of Material attractiveness of Np as a target material in (U,Np)3Si2 fuel

    三星夏海, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Development of a passive reactor shutdown device to prevent core damage accidents in fast reactors-Feasibility of the innovative device-idea and its nonproliferation features-

    川島正俊, 相楽洋, 守田幸路

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • The effect of nuclear fuel cycle scenario on TRU material balance and nuclear nonproliferation

    寺山正太郎, HAN Chi Young, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Non-proliferation features of Accelerator-Driven System using TRU fuel with separation resistance of an actinide element.

    山口紗希, 大泉昭人, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   42nd   2021

  • Design Study of Accelerator-Driven System with enhanced Non-proliferation Features using TRU-Silicide Fuel

    山口紗希, 大泉昭人, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Feasibility of Application of DDSI Assay Technique for Nuclear Material Quantification in Various Radioactive Waste Forms (2) Numerical analysis modeling and validation

    中岫翔, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Non-proliferation Features in Partitioning and Transmutation Cycle using Accelerator-driven System-Evaluation of Material Attractiveness of Fuel Assembly in Early Period of Burnup Cycle-

    大泉昭人, 大泉昭人, 菅原隆徳, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Development of Non-destructive Assay Technique using Passive Neutron Emission Tomography and Applicability for Partial Defect Verification

    徳田崇哉, 柴茂樹, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Institutional and Technical Measures for Rational Nuclear Safeguards of Next Generation Nuclear Fuel Cycle (2) Effect on Reduction of Person-Days of Inspection by New Partnership Approach

    筒井康二, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Development of core analysis model and evaluation of the nuclear fuel cycle mass balance in molten salt fast reactor

    青柳涼, 相楽洋, ASHRAF Osama, TIKHOMIROV Georgy, SMIRNOV Anton

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Feasibility study on small and medium modular light water reactors with inherent nuclear safety and non-proliferation features using U3Si3 fuel and RepU

    三星夏海, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Development of Image Reconstruction Technology using Passive Gamma Emission Tomography (3) Image reconstruction of passive gamma-ray source distribution of fuel debris in canister

    柴茂樹, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • Light Water Reactor Type Discrimination Method Using Fuel Nuclide Composition Information for Nuclear Forensics

    加賀山雄一, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   41st   2020

  • 核鑑識のための軽水炉由来照射済燃料核種組成の基本特性と判別指標の研究(1)研究計画

    加賀山雄一, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 東工大における原子力規制人材育成プログラム「原子力安全・核セキュリティ・保障措置教育の体系化と実践」(5)放射線災害対応実習

    HAN Chi Young, 江幡修一郎, 片渕竜也, 千葉敏, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • パッシブγ・中性子線断層撮影法を用いた非破壊測定技術の研究(1)使用済燃料由来パッシブ中性子線断層撮影法の部分欠損検認への適用の研究計画

    徳田崇哉, 柴茂樹, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 東京工業大学 原子力規制人材育成プログラム「原子力安全・核セキュリティ・保障措置教育の体系化と実践」(4)2019年度実施状況

    江幡修一郎, HAN Chi Young, 相楽洋, 松本義久, 千葉敏, 林崎規託, 池上雅子, 尾本彰, 竹下健二, 片渕竜也, 木倉宏成, 鷹尾康一郎

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 多様な放射性廃棄物内核物質量測定へのDDSI法の適用可能性(1)研究計画

    中岫翔, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 高い固有安全性・核セキュリティ性・核不拡散性を有する革新的中小型軽水炉の研究(1)MAおよび回収ウランを用いたシリサイド燃料

    三星夏海, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • パッシブγ線断層撮影法を用いた画像再構成技術の開発(2)モックアップ燃料集合体中γ線源分布の画像再構成

    柴茂樹, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 次世代核燃料サイクルの合理的な保障措置に向けた制度的・技術的方策に関する研究(1)研究計画

    筒井康二, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 溶融塩高速炉の核不拡散性に関する研究

    青柳涼, CHIRAYATH Sunil S., 相楽洋

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • 高い固有安全性・核不拡散性を有する軽水炉用燃料の研究(2)U-Puシリサイド燃料

    天野宰, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   40th   2019

  • パッシブγ線断層撮影法を用いた画像再構成技術の開発(1)統計的逐次近似法による使用済BWR燃料集合体中γ線源分布の画像再構成

    柴茂樹, 相楽洋

    日本核物質管理学会年次大会論文集(Web)   39th   2018

  • 高い固有安全性・核不拡散性を有する軽水炉用燃料の研究(1)プルトニウム混合シリサイド燃料

    天野宰, 相楽洋, HAN Chi Young, 藤縄主税

    日本核物質管理学会年次大会論文集(Web)   39th   2018

  • 高速炉サイクルシナリオによるTRU物質収支と核不拡散性への影響に関する研究(4)物質収支及び核不拡散性評価

    藤岡里英, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   39th   2018

  • 核分裂性アクチノイド核種の核特性データベースの作成(2)Ac~Cfの評価

    BARNG SooJun, 相楽洋, HAN Chi Young

    日本核物質管理学会年次大会論文集(Web)   39th   2018

  • 事故耐性燃料を用いた高安全性・高核拡散抵抗性を有する軽水炉の研究(2)U3Si2燃料の基本核特性

    藤縄主税, 相楽洋

    核物質管理学会日本支部年次大会論文集(Web)   37th   2016

  • 核分裂性アクチノイド核種の核特性データベースの作成(2)Ac~Cfの裸の臨界球の質量・崩壊熱・中性子放出量・放射線量

    BARNG Soo Jun, 相楽洋

    核物質管理学会日本支部年次大会論文集(Web)   37th   2016

  • 光核分裂反応に基づく核燃料物質同位体組成測定手法の計数比補正手法

    木村礼, 相楽洋, 千葉敏

    核物質管理学会日本支部年次大会論文集(Web)   37th   2016

  • パッシブγ線測定を用いたMOX軽水炉使用済燃料の簡便な燃焼度推定手法に関する研究

    鍋田陽之輔, 相楽洋

    核物質管理学会日本支部年次大会論文集(Web)   37th   2016

  • 超高速衝突に対する構造物の損傷機構の研究-超高速衝突問題の数値解析手法の信頼性向上に関する検討-

    菊原哲, 東出真澄, 片山雅英, 柳沢俊史, 相楽洋

    核物質管理学会日本支部年次大会論文集(Web)   37th   2016

  • 光核反応を用いた核燃料物質同位体組成測定手法の開発(1)原理確認

    木村礼, 相楽洋, 千葉敏

    核物質管理学会日本支部年次大会論文集(Web)   36th   2015

  • 随伴FPパッシブガンマ測定による燃料デブリ内核物質量推定可能性の検討(3)-簡便な燃焼度推定手法の提案-

    中原和基, 相楽洋, HAN Chi Young

    核物質管理学会日本支部年次大会論文集(Web)   36th   2015

  • 随伴FPパッシブガンマ測定による燃料デブリ内核物質量推定手法の現状報告

    芝知宙, 相楽洋, 檜山徹, 富川裕文

    核物質管理学会日本支部年次大会論文集(Web)   36th   2015

  • 核分裂性アクチノイド核種の核特性データベースの作成

    BARNG Soo Jun, 相楽洋

    核物質管理学会日本支部年次大会論文集(Web)   36th   2015

  • 随伴FPパッシブガンマ測定による燃料デブリ内核物質量推定可能性の検討(2)-仮想収納缶からの漏えいガンマ線特性-

    芝知宙, 相楽洋, 富川裕文

    核物質管理学会日本支部年次大会論文集(CD-ROM)   35th   2014

  • 多重被覆粒子燃料における効率的なTRU燃焼方法と3S特性の研究

    青木健, 相楽洋, HAN Chi Young

    核物質管理学会日本支部年次大会論文集(CD-ROM)   35th   2014

  • 高速炉サイクルシナリオによるTRU物質収支と使用済燃料の核不拡散性への影響に関する研究

    相楽洋, 中尾健志

    核物質管理学会日本支部年次大会論文集(CD-ROM)   35th   2014

  • 「核拡散抵抗性及び核物質防護評価:仮想的ナトリウム冷却高速炉ケーススタディ」の報告と考察

    相楽洋, 井上尚子, 川久保陽子, 綿引優

    核物質管理学会日本支部年次大会論文集(CD-ROM)   32nd   2011

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Presentations

  • Applicability of passive neutron non-destractive assay techniqe -neutron coincidence counting- for Pu quantification in MOX fuel containing MA

    Aya Eguchi, Hiroshi Sagara, Natsumi Mitsuboshi, Taketeru Nagatani

    AESJ 2025 Spring Mtg  2025.3 

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    Event date: 2025.3

    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Numerical Analysis of Photonuclear Reaction Detection using High Energy Gamma-ray from 7Li(p,g)8Be Triggered by Proton Accelerator International conference

    Krittanai Kiatkongkaew, Hiroshi Sagara, Kosuke Tanabe, Tatsuya Katabuchi, Chikako Ishizuka, Risa Kunitomo

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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  • Recycling RepU Containing Unseparated Np-237 to Improve the Sustainability and Proliferation-Resistance of Sodium-Cooled Fast Reactor Fuel Cycles International conference

    Hiroshi SAGARA

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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  • Estimating the origin of reprocessed Pu for Nuclear Forensics International conference

    Hayato Sato, Hiroshi Sagara, Chi Young Han, Yoshiki Kimura, Kosuke Tanabe

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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    Event date: 2025.1

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  • Development of a Detection Technique for Nuclear Materials Using Gamma-rays from the Proton-Lithium Nuclear Reaction International conference

    Tatsuya Katabuchi, Risa Kunitomo, Hiroshi Sagara, Chikako Ishizuka, Krittanai Kiatkongkaew, Kosuke Tanabe

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES),  2025.1 

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  • Evaluation of Measures for Enhancing the Efficiency of International Safeguards Activities Applied to SMRs International conference

    Koji Tsutsui, Hiroshi Sagara

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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  • Safeguards by design of sodium-cooled fast reactor with online re-fueling function International conference

    Shotaro Terayama, Hiroshi Sagara, Lisowski Eva

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025 

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    Event date: 2025.1

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  • Material Balance in MA Separation and Recycling for Environmental Load Reduction in Nuclear Fuel Cycle International conference

    Chi Young HAN, Hiroshi SAGARA, Hidekazu ASANO

    2025.1 

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  • Safety Properties of High-Temperature Gas-Cooled Reactor Core Layouts to Directly Reuse HALEU Spent Fuel International conference

    Hong Fatt Chong, Hiroshi Sagara

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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    Event date: 2025.1

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    Venue:Tokyo  

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  • Applicability of passive neutron non-destractive assay techniqe-neutron coincidence counting-for Pu quantification in MOX fuel containing MA

    江口綾, 相楽洋, 三星夏海, 長谷竹晃

    日本原子力学会春の年会予稿集(CD-ROM)  2025 

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  • 将来世代のための原子力の平和利用の3S に関する討議(2)核セキュリティの概念とその実装

    相樂洋

    核不拡散・保障措置・核セキュリティ連絡会、学生連絡会 合同セッション, 日本原子力学会2024年秋の大会  2024.9 

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    Event date: 2024.9

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

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  • Damage Mechanism of Reinforced Concrete Structures from Hypervelocity Projectile Impacts and Effects on Physical Protection System Performance

    Shu Inoue, Hiroshi Sagara

    AESJ 2024Annual Mtg  2024.3 

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    Event date: 2024

    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Identification of Key Signature Nuclides to Estimate the Origin of Reprocessed Pu for Nuclear Forensics

    佐藤颯, 相楽洋, HAN Chi Young, 木村祥紀, 田辺鴻典

    日本原子力学会秋の大会予稿集(CD-ROM)  2024 

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  • Study of on-site detection technique for nuclear materials concealed in heavy metals

    田辺鴻典, 米田政夫, 藤暢輔, 土屋兼一, 三澤毅, 北村康則, 相楽洋

    応用物理学会秋季学術講演会講演予稿集(CD-ROM)  2024 

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  • Neutronics and Safety Evaluation of Spent Fuel Direct Reuse in High-Temperature Gas-Cooled Reactor

    CHONG Hong Fatt, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2024 

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  • Impact of Uranium-silicide fuels on enhancement of fuel lifetime, nuclear safety and security in large scale LWRs

    森悠輔, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2024 

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  • Concept of Nuclear Security and its implementation

    相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2024 

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  • Reprocessed U silicide fuel loaded Boiling Water Reactors for nuclear non-proliferation and effective utilization of uranium resource

    Tomoki Azuma, Hiroshi Sagara

    AESJ 2024 Annual Mtg  2024.3 

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  • Recent Progress on Security-Safeguards of Small Modular Reactors

    Hiroshi Sagara

    44th Annual Mtg INNMJ  2023.11 

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    Event date: 2023.11

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  • Feasibility study on detection and verification of minor actinides by NDA technique based on photonuclear reactions International conference

    K. Tanabe, H. Sagara

    The 2023 IEEE NSS MIC RTSD  2023.11 

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  • Study on nuclear energy system considering environmental load reduction of waste disposal in diversification of nuclear fuel cycle conditions;(5)Environmental impact assessment of nuclear energy system and selection of nuclear fuel cycle options using cross-disciplinary approach and Multi-criteria Analysis International conference

    Hidekazu Asano, Tomofumi Sakuragi, Ryo Hamada, Chi Young Han, Masahiko Nakase, Tatsuro Matsumura, Go Chiba, Hiroshi SAGARA, KENJI TAKESHITA

    International Symposium on Zero-Carbon Energy Systems, IZES  2023.1 

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    Event date: 2023.1

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    Venue:Tokyo  

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  • Study on nuclear energy system considering environmental load reduction of waste disposal in diversification of nuclear fuel cycle conditions;(1)Evaluation of repository footprint and radiation effects in vitrified waste disposal using simplified MA separation International conference

    Ryo Hamada, Hidekazu Asano, Tomofumi Sakuragi, Chi Young Han, Masahiko Nakase, Tatsuro Matsumura, Go Chiba, Hiroshi SAGARA, KENJI TAKESHITA

    International Symposium on Zero-Carbon Energy Systems, IZES  2023.1 

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    Event date: 2023.1

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    Venue:Tokyo  

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  • Study on Nuclear Energy System Considering Environmental Load Reduction of Waste Disposal in Diversification of Nuclear Fuel Cycle Conditions;(4)Impact of the Spent Fuel Reprocessing Conditions on Fast Reactor Neutronics Property International conference

    Go Chiba, Hidekazu Asano, Tomofumi Sakuragi, Ryo Hamada, Chi Young Han, Masahiko Nakase, Tatsuro Matsumura, Hiroshi SAGARA, KENJI TAKESHITA

    International Symposium on Zero-Carbon Energy Systems, IZES  2023.1 

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    Event date: 2023.1

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    Venue:Tokyo  

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  • Study on Nuclear Energy System Considering Environmental Load Reduction of Waste Disposal in Diversification of Nuclear Fuel Cycle Conditions; (2) Impact of MA Separation and Recycle on the Material Balance of Nuclear Fuel Cycle International conference

    Chi Young HAN, Hiroshi SAGARA, Hidekazu ASANO, Tomofumi SAKURAGI, Ryo HAMADA, Go CHIBA, Masahiko NAKASE, Tatsuro MATSUMURA, Kenji TAKESHITA

    International Symposium on Zero-Carbon Energy Systems, IZES  2023.1 

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    Venue:Tokyo  

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  • Study on nuclear energy system considering environmental load reduction of waste disposal in diversification of nuclear fuel cycle conditions;(3)Simplification of MA separation process based on reasonable MA recovery rate by environmental impact assessment of radioactive waste disposal International conference

    Tatsuro Matsumura, Hidekazu Asano, Tomofumi Sakuragi, Ryo Hamada, Chi Young Han, Masahiko Nakase, Go Chiba, Hiroshi SAGARA, KENJI TAKESHITA

    International Symposium on Zero-Carbon Energy Systems, IZES  2023.1 

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    Venue:Tokyo  

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (13) Evaluations on core performance with candidate device specifications

    川島正俊, 相楽洋, 守田幸路, 有馬立身, LIU Wei, 有田裕二, 佐藤勇, 松浦治明, 関尾佳弘

    日本原子力学会秋の大会予稿集(CD-ROM)  2023 

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  • Passive safety of long-life small-medium sized transportable sodium cooled metal fuel fast reactors and challenges in its transportation

    岡崎陽香, 川島正俊, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2023 

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  • Development of offshore floating nuclear power (3) Vital area identification and path analysis on nuclear security

    Daisuke Hara, Hiroshi Sagara

    AESJ 2023 Fall Mtg  2023.9 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Spent Fuel Management Strategy of Prismatic Block Type HTGR by Its Direct Reuse

    Chong Hong Fatt, Hiroshi Sagara

    AESJ 2023 Fall Mtg  2023.9 

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (11) Overview of project progress

    Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

    AESJ 2023 Fall Mtg  2023.9 

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  • Study on Advanced Nuclear Energy System Based on the Environmental Impact of Radioactive Waste Disposal (11) Development of an Assessment Program of the MA Material Balance for Various Nuclear Fuel Cycle Options

    HAN Chi Young, 相楽洋, 朝野英一

    日本原子力学会春の年会予稿集(CD-ROM)  2023 

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  • Feasibility on offshore floating nuclear power plant in terms of 3S characteristics (1) The behavior of hyper-velocity jet in the water generated by shaped charge

    原大輔, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2023 

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (14) Evaluations on non-proliferation features of the passive shutdown devices

    相楽洋, 川島正俊, 守田幸路, 有馬立身, LIU Wei, 有田裕二, 佐藤勇, 松浦治明, 関尾佳弘

    日本原子力学会秋の大会予稿集(CD-ROM)  2023 

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  • Small and medium modular light water reactor with inherent nuclear safety and non-proliferation features-Evaluation of Nuclear Security-

    三星夏海, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2023 

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  • Study on Advanced Nuclear Energy System Based on the Environmental Impact of Radioactive Waste Disposal (5) Integrated Environmental Load Assessment for Diversifying Nuclear Fuel Cycle Conditions

    Hidekazu ASANO, Tomofumi SAKURAGI, Ryo HAMADA, Chi Young HAN, Masahiko NAKASE, Tatsuro MATSUMURA, Go CHIBA, Hiroshi SAGARA, Kenji TAKESHITA

    The AESJ 2022 Annual Meeting  2022.3 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Online  

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  • Study on Advanced Nuclear Energy System Based on the Environmental Impact of Radioactive Waste Disposal (7) Development of an Assessment Program of the Environmental Load of Radioactive Wastes for NFCSS

    Chi Young HAN, Hiroshi SAGARA, Hidekazu ASANO

    The AESJ 2022 Annual Meeting  2022.3 

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    Event date: 2022.3

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  • The advanced Nuclear 3S Education and Training(ANSET) Program of Tokyo Tech International conference

    Hiroshi Sagara

    Education as a Key to Addressing the Gender Equality Gap in Global Nuclear Security  2022.3 

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    Event date: 2022.3

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (7) Overview of overall project progress through FY2021

    守田幸路, LIU Wei, 有馬立身, 有田裕二, 佐藤勇, 松浦治明, 関尾佳弘, 相楽洋, 川島正俊

    日本原子力学会秋の大会予稿集(CD-ROM)  2022 

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  • Development Of Proliferation Resistance Evaluation Methodology And Its Applicability For The Offshore Floating Nuclear Power Plant

    Daisuke Hara, Hiroshi Sagara

    AESJ Spring Meeting 2022  2022.3 

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    Event date: 2022

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (10) Selection of the device assembly design effective in the reactivity control by its material relocation

    相楽洋, 守田幸路, 川島正俊, 有馬立身, LIU Wei, 有田裕二, 佐藤勇

    日本原子力学会秋の大会予稿集(CD-ROM)  2022 

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  • Neutronics and Non-proliferation features of Accelerator-Driven System using TRU fuel with separation resistance of an actinide element.

    山口紗希, 大泉昭人, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2022 

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  • Nuclear nonproliferation and security research and education at Tokyo Tech International conference

    Hiroshi SAGARA

    the international forum on peaceful use of nuclear energy, nuclear non-proliferation and nuclear security, “Nuclear Non-proliferation and nuclear security in the post COVID-19 era  2021.12 

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    Event date: 2021.12

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  • “Nuclear Forensics Signatures of Spent Nuclear Fuel-Signatures for discriminating reactor and fuel types-

    Yuichi KAGAYAMA, Hiroshi SAGARA, Chi Young HAN, Yoshiki KIMURA

    The AESJ 2021 Fall Meeting  2021.9 

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    Event date: 2021.9

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  • Study on Advanced Nuclear Energy System Based on the Environmental Impact of Radioactive Waste Disposal (1) Environmental Load and Nuclear Fuel Cycle Conditions in Waste Disposal

    Hidekazu ASANO, Tomofumi SAKURAGI, Ryo HAMADA, Chi Young HAN, Masahiko NAKASE, Tatsuro MATSUMURA, Go CHIBA, Hiroshi SAGARA, Kenji TAKESHITA

    The AESJ 2021 Annual Meeting  2021.3 

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    Event date: 2021.3

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    Venue:Online  

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  • Study on Advanced Nuclear Energy System Based on the Environmental Impact of Radioactive Waste Disposal (3) Applicability of NFCSS to Material Balance Evaluation of Nuclear Fuel Cycle

    Chi Young HAN, Hiroshi SAGARA, Hidekazu ASANO

    The AESJ 2021 Annual Meeting  2021.3 

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  • Development of a portable active neutron device using water Cherenkov detector

    田辺鴻典, 田辺鴻典, 米田政夫, 藤暢輔, 相楽洋

    アイソトープ・放射線研究発表会(Web)  2021 

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  • Nuclear non-proliferation features of ThF4-UF4 equilibrium fuel cycle with molten salt fast reactors

    青柳涼, 相楽洋, CHIRAYATH Sunil S.

    日本原子力学会春の年会予稿集(CD-ROM)  2021 

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  • Applicability of DDSI assay technique for Pu-240 effective mass quantification in Pu wastes including light-element impurities

    中岫翔, 相楽洋, HAN Chi Young, 長谷竹晃, 長谷竹晃

    日本原子力学会春の年会予稿集(CD-ROM)  2021 

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  • Nuclear Forensics Signatures of Spent Nuclear Fuel-Signatures for discriminating reactor and fuel types-

    加賀山雄一, 相楽洋, HAN Chi Young, 木村祥紀

    日本原子力学会秋の大会予稿集(CD-ROM)  2021 

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  • Applicability of Passive Neutron Emission Tomography to spent nuclear fuel assemblies (2) The effect of Water Rod on the tomography

    土屋克嘉, 相楽洋, HAN Chi Young

    日本原子力学会秋の大会予稿集(CD-ROM)  2021 

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (6) Specification of the device assembly design effective in the reactivity control by its material relocation

    Hiroshi SAGARA, Koji Morita, Masatoshi Kawashima, Tatemi Arima, Wei Liu, Yuji Arita, isamu sato

    AESJ Fall Meeting 2021  2021.9 

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    Event date: 2021

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (3) Overview of overall project progress through FY2020

    Koji Morita, Wei Liu, Ttemi Arima, Yuji Arita, isamu sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi SAGARA, Masatoshi Kawashima

    AESJ Fall Meeting 2021  2021.9 

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  • Applicability of Passive Neutron Emission Tomography to spent nuclear fuel assemblies

    Takaya Tokuda, Shigeki Shiba, Hiroshi Sagara

    AESJ 2020 Fall Meeting  2020.9 

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  • Feasibility study on innovative small and medium modular reactor with inherent nuclear safety and non-proliferation features (2) The effects of Uranium silicide fuel

    Natsumi Mitsuboshi, Hiroshi Sagara

    AESJ 2020 Fall Meeting  2020.9 

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  • Development of a passive reactor shutdown device to prevent core damage accidents in fast reactors (2) Fundamental evaluation of core features and the device response

    Hiroshi Sagara, Koji Morita, Masatoshi Kawashima, Wei Liu, Yuji Arita, isamu sato

    AESJ 2020 Fall Meeting  2020.9 

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    Event date: 2020.9

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  • Development of a passive safety shutdown device to prevent core damage accidents in fast reactors (1) Project overview

    Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Koharu Kawase, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi SAGARA, Masatoshi Kawashima

    AESJ 2020 Fall Meeting  2020.9 

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  • Feasibility Study on Small and Medium Pwr by Utilizing Uranium Silicide Fuel in the Aspects of Fundamental Neutronics, Inherent Safety, and Non-Proliferation Features International conference

    Natsumi Mitsuboshi, Hiroshi Sagara

    ICONE28-POWER2020  2020.8 

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  • Feasibility study on innovative small and medium modular reactor with inherent nuclear safety and non-proliferation features (1) Uranium silicide fuel with MA and/or RepU

    Natsumi Mitsuboshi, Hiroshi Sagara

    AESJ 2020 Fall Meeting  2020.3 

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    Event date: 2020.3

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  • Feasibility study on light water reactor using U-Pu silicide fuel with inherent safety and nonproliferation features

    Hiroshi SAGARA

    AESJ 2020 Annual Meeting  2020.3 

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  • Institutional and Technical Measures for Rational Nuclear Safeguards for Next Generation Nuclear Fuel Cycle - Case study on New Partnership Approach implemented by IAEA and Euratom -

    Koji Tsutsui, Hiroshi Sagara

    AESJ 2020 Annual Meeting  2020.3 

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  • Development of Image Reconstruction Technology using Passive Gamma Emission Tomography (2) Image Reconstruction of Gamma-ray Sources in Mock-up Fuel Assembly by Bayesian Iterative Approximation using Expectation Image and Image Recognition of Fuel Rods Using CNN

    柴茂樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2020 

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  • Application of Photofission Reaction to Identify Highly Enriched Uranium by Utilizing Bremsstrahlung Spectrum Photon

    Chin Kim Wei, Hiroshi SAGARA, Chi Young HAN, Rei KIMURA

    The AESJ 2019 Fall Meeting  2019.9 

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    Event date: 2019.9

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  • Applicability Study of Photofission Rate of Reaction Ratio Method to Identify High Enriched Uranium by Utilizing the Bremsstrahlung Spectrum Photon

    Chin Kim Wei, Hiroshi SAGARA, Chi Young HAN, Rei KIMURA

    The AESJ 2019 Annual Meeting  2019.3 

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    Event date: 2019.3

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  • Construction of Fundamental Nuclear Characteristics Databases of All Fissionable Actinide Nuclides

    Soojun BARNG, Hiroshi SAGARA, Chi Young HAN

    The AESJ 2019 Annual Meeting  2019.3 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Mito  

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  • 次世代炉,次世代燃料サイクルに関する保障措置・計量管理技術開発

    相楽洋, CHIRAYATH Sunil, CHIRAYATH Sunil

    日本原子力学会秋の大会予稿集(CD-ROM)  2019 

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  • パッシブγ線断層撮影法を用いた画像再構成技術の開発(1)ベイズ型逐次近似法によるモックアップ燃料集合体中γ線源分布の画像再構成

    柴茂樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2019 

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    Event date: 2019

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  • Nuclear Regulation Human Resources Development Program in Tokyo Tech “The Advanced Nuclear 3S Education and Training (ANSET)" (2) Implementation Status 2018

    Shuichiro EBATA, Chi Young HAN, Hiroshi SAGARA, Yoshihisa MATSUMOTO, Satoshi CHIBA, Noriyosu HAYASHIZAKI, Masako IKEGAMI, Akira OMOTO, Kenji TAKESHITA, Tatsuya KATABUCHI, Hiroshige KIKURA, Koichiro TAKAO

    The 39th Annual Meeting of INMM Japan Chapter  2018.11 

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    Event date: 2018.11 - 2019.11

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • User Interface Development of Atmospheric Dispersion Simulations for Nuclear Emergency Countermeasures

    Hamza EL-ASAAD, Hiroshi SAGARA, Chi Young HAN, Haruyasu Nagai

    The 39th Annual Meeting of INMM Japan Chapter  2018.11 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Tokyo  

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  • Nuclear Regulation Human Resources Development Program in Tokyo Tech “The Advanced Nuclear 3S Education and Training (ANSET)" (3) Exercise on Environmental Dynamics of Radioactive Material

    Chi Young HAN, Shuichiro EBATA, Hiroshi SAGARA, Kenji TAKESHITA, Yoshihisa MATSUMOTO, Satoshi CHIBA, Akiko FURUNO, Haruyasu Nagai

    The 39th Annual Meeting of INMM Japan Chapter  2018.11 

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    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • Applicability of LaBr3 (Ce) Detector for 154Eu Quantification in Molten Fuel Material and Waste Categorization by Using Passive Gamma

    Md Hanipah Nur Husna, Hiroshi SAGARA, Yoga Peryoga, Chi Young HAN

    The 39th Annual Meeting of INMM Japan Chapter  2018.11 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Tokyo  

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  • Effect of Fast Reactor Fuel Cycle Strategies on TRU Material Balance and Non-proliferation Features (4) Evaluation of Mass Balance and Non-proliferation Features

    Rie FUJIOKA, Hiroshi SAGARA, Chi Young HAN

    The 39th Annual Meeting of INMM Japan Chapter  2018.11 

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    Language:Japanese   Presentation type:Poster presentation  

    Venue:Tokyo  

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  • Optimization of PWR Core Design for Multipurpose Plutonium Utilization Strategies

    Rie FUJIOKA, Karim AMMAR, Frederic DAMIAN, Anthime FARDA, Hiroshi SAGARA, Chi Young HAN

    The AESJ 2018 Fall Meeting  2018.9 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Okayama  

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  • Sensitivity Analysis of Burnup Performance and Pu Mass Balance by Changing Core and Blanket Fuel Design of SFR for Flexible Pu Management Options International conference

    Rie FUJIOKA, Hiroshi SAGARA, Chi Young HAN

    The 26th International Conference on Nuclear Engineering (ICONE26)  2018.7 

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    Event date: 2018.7

    Language:English   Presentation type:Oral presentation (general)  

    Venue:London  

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  • Performance Evaluation of Light Water Reactor Fuel in Inherent Safety and Non-proliferation Features - U3Si2 Fuel -

    Chikara FUJINAWA, Hiroshi SAGARA, Chi Young HAN

    The AESJ 2018 Annual Meeting  2018.3 

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    Event date: 2018.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Osaka  

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  • 多目的のプルトニウム利用戦略に合わせたPWR炉心設計の最適化

    藤岡里英, AMMAR Karim, DAMIAN Frederic, FARDA Anthime, 相楽洋, HAN Chi Young

    日本原子力学会秋の大会予稿集(CD-ROM)  2018 

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  • 高い固有安全性・核不拡散性を有する軽水炉用燃料の研究-U3Si2燃料-

    藤縄主税, 相楽洋, HAN Chi Young

    日本原子力学会春の年会予稿集(CD-ROM)  2018 

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    Event date: 2018

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  • Nuclear data and its preparedness for developing non-destructive assay technique for non-proliferation and nuclear security - overview -

    Hiroshi SAGARA, Tatsuya Katabuchi

    2018.3 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • 再処理プロセスでのMA-Pu共存による臨界安全性、放射線安全性及び核不拡散性への包括的影響評価,

    渡辺 将矢, 相樂 洋

    原子力学会2017年春の年会  2017.3 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

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  • 高安全性・高核拡散抵抗性を有する軽水炉用FCM燃料の研究,

    和田 将樹, Sagara Hiroshi, HANCHI YOUNG

    原子力学会2017年春の年会  2017.3 

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  • Requirements for the accuracy of plutonium verification techniques in the TRU fuel cycle employing high,

    Takeshi Aoki, Hiroshi SAGARA, Chirayath S. Sunil

    2017.3 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • パッシブγ線測定を用いたMOX軽水炉使用済燃料の簡便な燃焼度推定手法に関する研究

    鍋田 陽之輔, 相樂 洋

    原子力学会2017年春の年会  2017.3 

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  • Characterization Study of Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Powe r Station (1) -General Outline-

    長谷 竹晃, 米田 政夫, 芝 知宙, 名内 泰志, 相樂 洋, 小菅 義広, 奥村 啓介, 前田 亮, 藤 暢輔, 堀 啓一郎

    2017.3 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Estimation Technique of Cs Retention Fraction in Fuel Debris

    Hiroshi SAGARA, Kazuki NAKAHARA, Chi Young HAN

    The AESJ 2017 Annual Meeting  2017.3 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Characterization Study of Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Power Station (4) Passive γ Method

    芝 知宙, Hiroshi SAGARA, 富川 裕文

    2017.3 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • 福島第一原子力発電所における燃料デブリ中の核燃料物質定量に関する候補技術の特性研究 II-(3)パッシブガンマ法-

    芝知宙, 相楽洋, 富川裕文

    日本原子力学会秋の大会予稿集(CD-ROM)  2017 

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  • 核セキュリティの立場からのデータニーズ

    相樂 洋

    日本原子力学会2017年秋の大会「シグマ」特別専門委員会 特別講演  2017.9 

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    Event date: 2017

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

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  • 再処理プロセスでのMA-Pu共存による臨界安全性,放射線安全性及び核不拡散性への包括的影響評価

    渡辺将矢, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2017 

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  • 高安全性・高核拡散抵抗性を有する軽水炉用FCM燃料の研究

    和田将樹, 相楽洋, HAN Chi Young

    日本原子力学会春の年会予稿集(CD-ROM)  2017 

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  • パッシブγ線測定を用いた燃料デブリ中Csの簡便な残存率推定手法

    相楽洋, 中原和基, 中原和基, HAN Chi Young

    日本原子力学会春の年会予稿集(CD-ROM)  2017 

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  • 事故耐性燃料を用いた高安全性・高核拡散抵抗性を有する軽水炉の研究(1)FCM 燃料の基本核特性,

    和田, 相樂, Chi Young Han

    第37回核物質管理学会日本支部年次大会  2016.11 

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    Event date: 2016.11

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  • 高速炉サイクルシナリオによるTRU 物質収支と核不拡散性への影響に関する研究(3)分離Pu の照射Pu への迅速な転換のための高速炉炉心設計,”

    藤岡 里英, 相樂 洋, Chi Young Han

    第37回核物質管理学会日本支部年次大会  2016.11 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Academy for Global Nuclear Safety and Security Agent (2) Nuclear Safety and Security Courses, I Measurement of Environmental Radiation”

    Yoshihisa Matsumoto, Masayuki Igashira, Yoshiyuki Oguri, Satoshi Chiba, Chi Young Han, Hiroshi Sagara

    2016.11 

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    Language:Japanese   Presentation type:Oral presentation (general)  

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  • Characterization Study of Nuclear Material Quantification Technologies for Fuel Debris at Fukushima Daiichi Nuclear Power Station (4) –Passive Gamma Technique- (interim report)

    Tomooki SHIBA, Hiroshi SAGARA, Hirofumi TOMIKAWA

    2016.11 

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  • Benchmark Calculations for Evaluation of Gamma Spectrometer Efficiency Using PHITS Code

    Nur Husan MD Hanipah, Yoga Peryoga, Hiroshi Sagara, Chi Young Han, Tomooki Shiba, “

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • パッシブγ線測定を用いたMOX 軽水炉使用済燃料の簡便な燃焼度推定手法に関する研究,

    鍋田, 相樂

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • 再処理プロセスでのMA-Pu 共存による臨界安全性、放射線安全性及び核不拡散性への包括的影響評価

    渡辺将矢, 相樂洋

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • 光核分裂反応に基づく核燃料物質同位体組成測定手法の計数比補正手法

    木村礼, 相樂洋, 千葉敏

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • Utilization of Atmospheric Dispersion Simulations for Nuclear Emergency Countermeasures

    H. ElAsaad, Nagai, 相樂 洋

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • Limit of detection of a bare nuclear material debris lump

    Yoga Peryoga, Hiroshi Sagara, Tomooki Shiba

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • Academy for Global Nuclear Safety and Security Agent (3) Nuclear Safety and Security Courses, II Nuclear Security Training”

    Hiroshi Sagara1, Koichiro Takao1, Masahide Katayama2, Yosuke Naoi3, Hironobu Nakamura3, Chi Young Han1

    2016.11 

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  • 超高速衝突に対する堅牢生向上のための構造物の損傷機構の研究‐超高速衝突問題の数値解析手法の信頼性向上に関する検討‐

    菊原, 東出, 片山, 柳沢, 相樂洋

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • Characterization Study of Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Power Station (1) –General Outline-

    長谷 竹晃, 米田 政夫, 芝 知宙, 前田 亮, 名内 泰志, 呉田 昌俊, 富川 裕文, 奥村 啓介, Hiroshi SAGARA, 小菅 義広, Cynthia HEINBERG, 堀 啓一郎

    2016.11 

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  • 事故耐性燃料を用いた高安全性・高核拡散抵抗性を有する軽水炉の研究(2)U3Si2 燃料の基本核特性

    藤縄, 相樂

    第37回核物質管理学会日本支部年次大会  2016.11 

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  • User Interface of Atmospheric Dispersion Simulation for Nuclear Emergency Countermeasures

    H. El-Asaad, H. Sagara, H. Nagai

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • Consideration of Enhanced Safety Based on CMR-concept for Large Fast Reactor” International conference

    Masatoshi Kawashima, Hiroshi Sagara

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • PHITS Benchmarking for HPGe Detector Efficiency International conference

    Peryoga Yoga, Hiroshi Sagara, Tomooki Shiba

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Language:English   Presentation type:Oral presentation (general)  

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  • Applicability Study of the Photofission Based Nuclear Material Isotopic Composition Measurement Method on the Thorium Uranium System International conference

    Rei Kimura, Hiroshi Sagara, Satoshi Chiba

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • Simple Method to Create Gamma Ray Source Spectrum for Passive Gamma Technique International conference

    T. Shiba, H. Tomikawa, H. Sagara, A. Ishimi

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • Characterization Study of Four Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Power Station International conference

    T. Nagatani, M. Komeda, T. Shiba, M. Maeda, Y. Nauchi, M. Kureta, H. Tomikawa, K. Okumura, H. Sagara, C. Heinberg, K. Hori

    The 5th International Symposium on Innovative Nuclear Energy Systems  2016.10 

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    Language:English   Presentation type:Oral presentation (general)  

    Venue:Tokyo  

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  • Nuclear Non-proliferation Safeguards International conference

    Hiroshi SAGARA

    Nuclear Engineering Intensive Course in cooperation with Kaunas University of Technology 6th Term  2016.3 

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    Event date: 2016.3

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

    Venue:Kaunas  

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  • Nuclear Non-proliferation Nuclear Security International conference

    Hiroshi SAGARA

    Nuclear Engineering Intensive Course in cooperation with Kaunas University of Technology 6th Term  2016.3 

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

    Venue:Kaunas  

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  • 高速炉サイクルシナリオによるTRU物質収支と核不拡散性への影響に関する研究(1)分離Puの照射Puへの迅速な転換シナリオ

    藤岡里英, 相楽洋, HAN Chi Young

    日本原子力学会春の年会予稿集(CD-ROM)  2016 

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  • 大型高速炉におけるCMR概念の適用による安全強化方策の考察-液体金属燃料デバイス概念による炉心反応度評価事例-

    川島正俊, 原昭浩, 坪井靖, 守田幸路, 遠藤寛, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2016 

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  • 多重被覆粒子燃料における効率的なPu燃焼方法と3S特性の評価

    青木健, 相楽洋, HAN Chi-Young

    日本原子力学会春の年会予稿集(CD-ROM)  2015 

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  • BWR使用済燃料放射線のパッシブ測定を用いた簡便な燃焼度及び核物質量推定手法に関する研究

    中原和基, 相楽洋, HAN Chi Young

    日本原子力学会春の年会予稿集(CD-ROM)  2015 

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  • 随伴FPパッシブガンマ測定による燃料デブリ内核物質量推定可能性の検討

    相楽洋, 芝知宙, 中原和基, 富川裕文

    日本原子力学会春の年会予稿集(CD-ROM)  2015 

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  • 東京工業大学における核不拡散・核セキュリティ研究及び教育

    相楽洋, 韓治暎

    日本原子力学会秋の大会予稿集(CD-ROM)  2015 

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  • 「グローバル原子力安全・セキュリティ・エージェント養成」(3)原子力安全・セキュリティ実習科目群

    木倉宏成, 相楽洋, 韓治暎, 井頭政之, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2015 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の基礎研究

    齊藤正樹, 小澤正基, 韓治暎, 相楽洋, 芝知宙, 中尾健志, 小山真一, 大林弘, 田中康介, 大西貴士

    日本原子力研究開発機構JAEA-Review(Web)  2014 

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  • 高速増殖炉の多重サイクルにおける物質収支と核拡散抵抗性に関する研究

    中尾健志, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2014 

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  • 放射性ランタノイドの添加による核拡散抵抗性の高い革新的な核燃料に関する研究

    谷宜憲, HAN Chi Young, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2013 

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  • 高い核拡散抵抗性を有するPu生成のための高速炉ブランケット燃料への減速材装荷方法と効果

    山内一平, 相楽洋, 齊藤正樹, 大西貴士

    日本原子力学会春の年会予稿集(CD-ROM)  2013 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(XV)劣化ウラン-アメリシウムペレットの照射挙動予測

    芝知宙, 相楽洋, HAN Chi Young, 齊藤正樹, 大西貴士, 小山真一, 前田茂貴

    日本原子力学会秋の大会予稿集(CD-ROM)  2013 

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  • Cm-244の中性子共鳴捕獲反応を利用した黒鉛減速ガス冷却炉の高燃焼度化

    遠山勇樹, 齊藤正樹, HAN Chi Young, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2012 

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  • 高速増殖炉ブランケットにおける高い核拡散抵抗性を有するPuの生成に及ぼす減速材装荷手法の影響

    松本航治, 相楽洋, HAN Chi Young, 齊藤正樹, 大西貴士

    日本原子力学会春の年会予稿集(CD-ROM)  2012 

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  • 核反応による希土類の創生とリサイクルに関する予備的検討

    小澤正基, 吉岡斗志雄, 小山真一, 相楽洋, 齊藤正樹

    希土類  2011 

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  • 重水炉を用いた使用済燃料の再利用性と核拡散抵抗性の評価

    大西絢也, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2011 

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  • 軽水炉級Am及びCmを装荷した超長寿命宇宙用原子炉概念の検討(2)-鉛ビスマス反射体の燃焼特性への影響-

    中村正則, 齊藤正樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2011 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(XII)-「常陽」照射Uサンプルの分析(4)-

    大西貴士, 小山真一, 前田茂貴, 相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • 核拡散抵抗性-核分裂性物質の魅力度(1)-

    齊藤正樹, 木村祥紀, 浜瀬枝里菜, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • 軽水炉級Am及びCmを装荷した超長寿命宇宙用原子炉概念の検討

    中村正則, 齊藤正樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • MA添加による内部ブランケットを有する高速増殖炉の長寿命化の研究

    浜瀬枝里菜, 齊藤正樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究-(XI)U-Amペレット照射予測解析-

    相楽洋, 芝知宙, 齊藤正樹, 前田茂貴, 小山真一

    日本原子力学会春の年会予稿集(CD-ROM)  2010 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(IX)-「常陽」照射Uサンプルの分析(3)-

    大西貴士, 須藤光雄, 小山真一, 関岡健, 芝知宙, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2010 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究

    相楽洋, 齊藤正樹, 芝知宙, 田中健哉, 小山真一, 大林弘, 須藤光雄, 大川内靖

    日本原子力研究開発機構JAEA-Review(Web)  2010 

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  • 強い核拡散抵抗性を有するPu生成の実証試験とMA核データの確認

    相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • Numerical Analysis of Irradiated Am Samples in Experimental Fast Reactor Joyo

    Hiroshi Sagara, Tetsuro Yamamoto, Shin-ichi Koyama, Shigetaka Maeda, Tomo-oki Shiba, Masaki Saito

    ACTINIDES 2009  2010 

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  • 中性子共鳴捕獲反応を利用したTRU燃料の燃焼反応度の低減化

    酒井健, 相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2010 

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  • ATR 2A/2B As-Run Neutronics Uncertainty Analysis

    Hiroshi SAGARA, Gray Chang

    INL/EXT-09-17197  2009.10  INL/EXT-09-17197

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    Event date: 2009.10

    Language:English  

    Summary report of activities of FUJI-A assignee Hiroshi Sagara.

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  • Transmutation of Sn-126 in Spallation Targets of Accelerator-Driven Systems

    Chi Young Han, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2009.1 

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  • Transmutation of Sn-126 in Spallation Targets of Accelerator-Driven Systems

    Chi Young Han, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2009.1 

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  • ATR 2A/2B As-Run Neutronics Uncertainty Analysis

    Hiroshi Sagara, Gray S. Chang

    INL/EXT-09-17197  2009 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(VI)「常陽」照射Uサンプルの分析(2)

    大西貴士, 須藤光雄, 大林弘, 小山真一, 田中健哉, MEILIZA Yoshitalia, 山本哲郎, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2009 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(VII)-サンプルの核変換特性解析(3)-

    山本哲郎, 相楽洋, 齊藤正樹, 小山真一, 大西貴士, 大川内靖

    日本原子力学会春の年会予稿集(CD-ROM)  2009 

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  • 核拡散抵抗性を有するPuを生成する燃料概念の構築 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究

    田中健哉, 小山真一, 大林弘, 須藤光雄, 大川内靖, 相楽洋, 齊藤正樹, YOSHITALIA Meiliza, 山本哲郎, 佐合優一

    日本原子力研究開発機構JAEA-Review  2009 

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  • 高速増殖炉におけるPuの改質に関する研究

    浜瀬枝里菜, 齊藤正樹, 相楽洋

    日本原子力学会春の年会予稿集(CD-ROM)  2009 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(VIII)-「常陽」照射Amサンプルの分析(1)-

    大西貴士, 須藤光雄, 小山真一, 田中健哉, 関岡健, 芝知宙, 相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2009 

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  • 高い核拡散抵抗性を有するPuを生成する高速増殖炉の研究-Am及びCmの効果-

    佐合優一, 齊藤正樹, 相楽洋, MEILIZA Yoshitalia

    日本原子力学会春の年会予稿集(CD-ROM)  2009 

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  • Enhancement of Plutonium Proliferation Resistance by Transmutation of Minor Actinide- Plutonium Denaturing by Decay Heat-

    Y. Kimura, H. Sagara

    Trans Ame Nucl Society Winter Mtg 2008  2008.11 

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    Language:English  

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  • Feasibility of Reprocessed Uranium in LWR Fuel Cycle for Protected Plutonium Production

    Kosaku Fukuda, Hiroshi Sagara, Masaki Saito, Tsunetomo Mitsuhashf

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.10 

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  • Radiation Dose as a Barrier against Proliferation for Advanced Fuel Compositions

    Vladimir Artisyuk, Masaki Saito, Alan Takibayev, Fliroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.10 

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  • Feasibility of Reprocessed Uranium in LWR Fuel Cycle for Protected Plutonium Production

    Kosaku Fukuda, Hiroshi Sagara, Masaki Saito, Tsunetomo Mitsuhashf

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.10 

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  • Radiation Dose as a Barrier against Proliferation for Advanced Fuel Compositions

    Vladimir Artisyuk, Masaki Saito, Alan Takibayev, Fliroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.10 

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  • Abstract of 2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity

    H. Sagara

    Abstract of 2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008.9 

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    Event date: 2008.9

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  • Protected plutonium breeding by transmutation of minor actinides in fast breeder reactor

    Yoshitalia Meiliza, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.3 

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    Event date: 2008.3

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  • Protected plutonium breeding by transmutation of minor actinides in fast breeder reactor

    Yoshitalia Meiliza, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2008.3 

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    Event date: 2008.3

    Language:English  

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(III)-サンプルの核変換特性解析(1)-

    相楽洋, 山本哲郎, 齊藤正樹, 小山真一

    日本原子力学会春の年会予稿集(CD-ROM)  2008 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究

    相楽洋, 齊藤正樹, YOSHITALIA Meiliza, 山本哲郎, 佐合優一, 田中健哉, 小山真一, 大林弘, 須藤光雄, 関根隆

    日本原子力研究開発機構JAEA-Review  2008 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(II)「常陽」照射Uサンプルの分析(1)

    小山真一, 須藤光雄, 大林弘, MEILIZA Yoshitalia, 相楽洋, 齊藤正樹

    日本原子力学会春の年会予稿集(CD-ROM)  2008 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)-(XIV)核拡散抵抗性評価手法の開発-

    齊藤正樹, ARTISYUK V., TAKIBAYEV A., 相楽洋, PERMANA S., MEILIZA Y., ISMAILOV K.

    日本原子力学会秋の大会予稿集(CD-ROM)  2008 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)-(XII)ATR照射解析-

    相楽洋, 齊藤正樹, 小山真一, 伊藤正彦, 北村了一

    日本原子力学会秋の大会予稿集(CD-ROM)  2008 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(I)全体計画

    相楽洋, 小山真一

    日本原子力学会春の年会予稿集(CD-ROM)  2008 

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  • Perspectives of inventories of secondary nuclear materials generated in the nuclear energy production and mass balance in PPP cycle

    K. Fukuda, Y. Peryoga, H. Sagara, M. Saito, M. Ceyhan

    PROGRESS IN NUCLEAR ENERGY  2008 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(V)-サンプルの核変換特性解析(2)-

    山本哲郎, 相楽洋, 齊藤正樹, 小山真一

    日本原子力学会秋の大会予稿集(CD-ROM)  2008 

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  • Abstract of 2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity

    M. Saito, H. Sagara

    Abstract of 2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008 

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  • Perspectives of inventories of secondary nuclear materials generated in the nuclear energy production and mass balance in PPP cycle

    K. Fukuda, Y. Peryoga, H. Sagara, M. Saito, M. Ceyhan

    PROGRESS IN NUCLEAR ENERGY  2008 

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  • Enhancement of Plutonium Proliferation Resistance by Transmutation of Minor Actinide- Plutonium Denaturing by Decay Heat-

    Y. Kimura, M. Saito, H. Sagara

    2008 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)(XI)ATR照射・照射後試験

    小山真一, 北村了一, 伊藤正彦, 相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2008 

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  • Application of fusion neutron source for denaturing of plutonium

    Alan Takibayev, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2007.8 

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    Event date: 2007.8

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  • Application of fusion neutron source for denaturing of plutonium

    Alan Takibayev, Masaki Saito, Hiroshi Sagara

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2007.8 

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  • 高い核拡散抵抗性を有するPu生成に及ぼす236Uの影響

    三橋庸智, 福田幸朔, 相楽洋, 齊藤正樹

    日本原子力学会春の年会要旨集(CD-ROM)  2007 

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  • プルトニウムの核拡散抵抗性-Attractivenessについて-

    齊藤正樹, 相楽洋, TAKIBAYEV A., ISMAILOV K., MEILIZA Y., ARTISYUK V.

    日本原子力学会秋の大会予稿集(CD-ROM)  2007 

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  • Denaturing of Plutonium by Transmutation of Minor-Actinides -Effect of uranium-free-fuel-

    Hiroshi SAGARA, Masaki SAITO

    Bulletin, Tokyo Tech  2006.3 

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    Event date: 2006.3

    Language:English  

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  • マイナーアクチナイド核変換によるプルトニウムの核拡散抵抗性の強化

    相楽 洋

    学位論文 東京工業大学  2006.3 

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    Language:Japanese  

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  • Th-U-TRU混合燃料を用いた高い核拡散抵抗性を有する原子力システムの研究

    相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2006 

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  • Denaturing of Plutonium by Transmutation of Minor-Actinides -Effect of uranium-free-fuel-

    Hiroshi SAGARA, Masaki SAITO

    Bulletin, Tokyo Tech  2006 

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  • Protected Plutonium Production by Doping MA in Blanket of Fast Breeder Reactor -Effect of ZrH2-

    Yoshitalia MEILIZA, Masaki SAITO, Hiroshi SAGARA

    Bulletin, Tokyo Tech  2006 

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  • Protected Plutonium Production by Doping MA in Blanket of Fast Breeder Reactor -Effect of ZrH2-

    Yoshitalia MEILIZA, Masaki SAITO, Hiroshi SAGARA

    Bulletin, Tokyo Tech  2006 

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  • 天然U-MA燃料における核拡散抵抗性の高いPuの生成

    谷口卓郎, 相楽洋, 齊藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2006 

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  • Inherent protection of plutonium by doping minor actinide in thermal neutron spectra

    Y Peryoga, H Sagara, M Saito, A Ezoubtchenko

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2005.5 

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    Event date: 2005.5

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  • Inherent protection of plutonium by doping minor actinide in thermal neutron spectra

    Y Peryoga, H Sagara, M Saito, A Ezoubtchenko

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2005.5 

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  • Denaturing of plutonium by transmutation of minor-actinides for enhancement of proliferation resistance

    H Sagara, M Saito, Y Peryoga, A Ezoubtchenko, A Takivayev

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2005.2 

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  • Denaturing of plutonium by transmutation of minor-actinides for enhancement of proliferation resistance

    H Sagara, M Saito, Y Peryoga, A Ezoubtchenko, A Takivayev

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY  2005.2 

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  • Proliferation resistance properties of U and Pu isotopes

    AA Ezoubtchenko, M Saito, VV Artisyuk, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • Fusion-driven transmutation of selected long-lived fission products

    A Takibayev, M Saito, Artisyuk, V, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • MA核変換を利用したPuの改質に関する研究(V)-加速器駆動システムによる軍事用プルトニウムの改質-

    日高一誠, 斉藤正樹, 相楽洋

    日本原子力学会秋の大会予稿集(CD-ROM)  2005 

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  • Proliferation resistance properties of U and Pu isotopes

    AA Ezoubtchenko, M Saito, VV Artisyuk, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • Improvement of plutonium proliferation resistance by doping minor actinides

    Y Peryoga, M Saito, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • Improvement of plutonium proliferation resistance by doping minor actinides

    Y Peryoga, M Saito, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • Fusion-driven transmutation of selected long-lived fission products

    A Takibayev, M Saito, Artisyuk, V, H Sagara

    PROGRESS IN NUCLEAR ENERGY  2005 

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  • MA核変換を利用したPuの改質に関する研究(IV)-マスバランスの予備評価-

    相楽洋, 斉藤正樹

    日本原子力学会秋の大会予稿集(CD-ROM)  2005 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)(X)-Np添加方法とマスバランス-

    斎藤正樹, 相楽洋, ARTISHYUK V, 貝瀬与一郎

    日本原子力学会秋の大会予稿集  2004 

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  • MA核変換を利用したPuの改質に関する研究(III)-加速器駆動システム-

    福永崇紀, 斉藤正樹, 相楽洋, 佐々敏信

    日本原子力学会秋の大会予稿集  2004 

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  • Transmutation of long-lived fission products driven by D-T and D-D fusion: Specific neutronics and radiological consequences

    A Stankovsky, M Saito, VV Artissiouk, AN Shmelev, H Sagara

    FUSION SCIENCE AND TECHNOLOGY  2003.6 

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    Event date: 2003.6

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  • Transmutation of long-lived fission products driven by D-T and D-D fusion: Specific neutronics and radiological consequences

    A Stankovsky, M Saito, VV Artissiouk, AN Shmelev, H Sagara

    FUSION SCIENCE AND TECHNOLOGY  2003.6 

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  • Characterization of individual fission products in terms of their production and transmutation

    Hiroshi Sagara, Tadashi Yoshida, Masaki Saito

    International Conference on Nuclear Engineering, Proceedings, ICONE  2002 

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  • AIDS患者に発症した悪性リンパ腫小腸転移穿孔の1例

    牧野洋知, 高橋正純, 相楽裕子, 橋本邦夫, 小金井一隆, 石山暁, 鬼頭文彦, 福島恒男

    日本臨床外科学会雑誌  2000 

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  • Role of Minor Actinides for Protected Plutonium Production (P3) (III) Application of P3 in LWR with Pu fuel -

    Tokyo Tech COE-INES Indonesia Ineternational Symposium 2005, Prospect of Nuclear Energy in Indonesia  2005 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究-(X)サンプルの核変換特性解析(4)-

    芝 知宙, 相樂洋, 前田 茂貴, 小山 真一

    日本原子力学会2010年春の年会  2010.3 

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    Venue:茨城県水戸市  

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  • 広い中性子スペクトルにおけるマイナーアクチノイド核変換によるプルトニウムの核拡散抵抗性の向上

    木島 佑一, 相樂洋

    日本原子力学会2010年春の年会  2010.3 

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    Venue:茨城大学  

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(Ⅸ)-「常陽」照射Uサンプルの分析(3)-

    大西 貴士, 須藤 光雄, 小山 真一, 関岡 健, 芝 知宙, 相樂洋

    日本原子力学会2010年春の年会  2010.3 

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    Venue:茨城県水戸市  

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  • 高い核拡散抵抗性を有するPu を生成する高速炉ブランケット燃料の研究-(XI) U-Am ペレット照射予測解析 -

    相樂洋, 芝 知宙, 前田 茂貴, 小山 真一

    日本原子力学会2010年春の年会  2010.3 

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    Venue:茨城県水戸市  

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  • Advanced Nuclear 3S Education and Training - Overview and Curriculum - International conference

    Hiroshi Sagara

    INSEN 2018 Annual Meeting  2018.7 

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    Venue:Vienna  

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  • Effect of photon absorption adjusting on nuclear fuel material isotopic composition measurement based on the photofission reaction

    Rei Kimura, Hiroshi SAGARA, Satoshi Chiba

    2017.11 

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  • User Interface Development of Atmospheric Dispersion Simulations for Nuclear Emergency Countermeasures (II). Evaluation of Interface Application for Fukushima Daiichi Disaster Case Scenario

    Hamza El-Asaad, Haruyasu Nagai, Hiroshi Sagara, Chi Young Han

    第38回日本核物質管理学会年次大会  2017.11 

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    Venue:東京  

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  • Feasibility study of TRISO fuel for efficient Pu incineration and 3S feature enhancement (3) Required measurement accuracy for the Pu verification technique

    Takeshi Aoki, Hiroshi Sagara, Sunil S. Chirayath

    2017.11 

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  • Characterization Study of Candidate Technologies for Nuclear Material Quantification in Fuel Debris at Fukushima Daiichi Nuclear Powe r Station (1) -General Outline-

    長谷 竹晃, Masao Komeda, 芝 知宙, 名内 泰志, Hiroshi SAGARA, 小菅 義広, 奥村 啓介, 前田 亮, Yosuke Toh, 堀 啓一郎

    2017.3 

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  • Denaturing of Plutonium by Transmutation of Minor Actinides

    9-th International Conference “Nuclear Safety & Nuclear Education” Obninsk, Russia, 24-27 October 2005  2005 

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  • Experience of Graduate School in Tokyo Institute of Technology

    The 1st International Workshop "Russia-Japan International Research Cooperation and Nuclear Education Toward Innovative Nuclear Energy Systems"  2005 

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  • Application of Fusion Neutron Source for Denarturing of Plutonium

    9-th International Conference Nuclear Safety & Nuclear Education Obninsk, Russia, 24-27 Octobar 2005  2005 

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  • Role of Minor Actinides for Protected Plutonium Production (P3) (III) Application of P3 in LWR with Pu fuel -

    Tokyo Tech COE-INES Indonesia Ineternational Symposium 2005, Prospect of Nuclear Energy in Indonesia  2005 

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  • Denaturing of Plutonium by Transmutation of Minor Actinides

    2005 

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  • MA核変換を利用したPuの改質に関する研究(IV) -マスバランスの予備評価-

    日本原子力学会秋の年会2005  2005 

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  • Prospects of Inventories of U, Pu and MAs and Mass Blance in PPP Cycle

    2005 

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  • Protected Plutonium Production by Doping MA in Blanket Region of Fast Breeder Reactor Effect of ZrH2

    日本原子力学会秋の年会2005  2005 

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  • Denaturing of Plutonium by Transmutation of MA (VI) Fusion Neutron Source

    日本原子力学会秋の年会2005  2005 

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  • Denaturing of Plutonium by Transmutation of Minor Actinides

    9-th International Conference “Nuclear Safety & Nuclear Education” Obninsk, Russia, 24-27 October 2005  2005 

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  • Experience of Graduate School in Tokyo Institute of Technology

    The 1st International Workshop "Russia-Japan International Research Cooperation and Nuclear Education Toward Innovative Nuclear Energy Systems"  2005 

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  • Application of Fusion Neutron Source for Denarturing of Plutonium

    9-th International Conference Nuclear Safety & Nuclear Education Obninsk, Russia, 24-27 Octobar 2005  2005 

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  • MA核変換を利用したPuの改質に関する研究(II)-Inert Matrix材料の効果-

    相楽洋, 齊藤正樹

    日本原子力学会秋の年会(2004)予稿集  2004.9 

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  • MA核変換を利用したPuの改質に関する研究(III)-加速器駆動システム

    福永崇紀, 齊藤正樹, 相楽洋, 佐々敏信

    日本原子力学会秋の年会(2004)予稿集  2004.9 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)(X) −Np添加方法とマスバランス−

    貝瀬與一郎, 齋藤正樹, 相楽洋, Vladimir Artishyuk

    本原子力学会秋の年会(2004)  2004.9 

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  • Development of Innovative Nuclear technology to Produce Protected Plutonium with high Proliferation Resistance (P3 - Project) - Grand Design of Project -

    American Nuclear Society Winter Mtg. 2004  2004 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画)(X) -Np添加方法とマスバランス-

    本原子力学会秋の年会(2004)  2004 

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  • Denaturation of Plutonium by Transmutation of Minor Actinides

    INES1  2004 

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  • Development of Innovative Nuclear technology to Produce Protected Plutonium with high Proliferation Resistance (P3 - Project) - Grand Design of Project -

    American Nuclear Society Winter Mtg. 2004  2004 

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  • Denaturation of Plutonium by Transmutation of Minor Actinides

    INES1  2004 

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  • 加速器駆動炉を用いたマイナーアクチニドの核変換に関する研究

    山口隆太, 齊藤正樹, V. Artisyuk, 相楽洋

    日本原子力学会春の年会(2003)予稿集  2003.3 

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  • MA核変換を利用したPuの改質に関する研究

    相楽洋, V. Artisyuk, 齊藤正樹, 山口隆太

    日本原子力学会春の年会(2003)  2003.3 

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  • Characterization of Individual Fission Products in terms of their Production and Transmutation

    ANS Student Conf., Pen. St. Univ., PA, Apr. 10-14  2002 

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  • Characterization of Individual Fission Products in terms of their Production and Transmutation

    ANS Student Conf., Pen. St. Univ., PA, Apr. 10-14  2002 

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  • Transmutation Capability of a Once-through Molten-salt and Other Transmuting Reactors

    Topical Mtg. on Accelerator Appl.  2001 

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  • Transmutation Capability of a Once-through Molten-salt and Other Transmuting Reactors

    Topical Mtg. on Accelerator Appl.  2001 

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  • 核分裂生成物の固有消滅特性

    相楽洋, 吉田正

    日本原子力学会秋の年会(1999)  1999.9 

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  • Denaturing of Plutonium by Transmutation of Minor Actinides

    2005 

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  • Prospects of Inventories of U, Pu and MAs and Mass Blance in PPP Cycle

    2005 

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  • Effect of 236U on Protected Plutonium Production

    10th International Conference Nuclear Power Safety and Nuclear Education  2007 

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  • 高い核拡散抵抗性を有するPu生成に及ぼす236Uの影響

    日本原子力学会2007年春の年会予稿  2007 

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  • プルトニウムの核拡散抵抗性-Attractiveness-

    2007 

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  • Feasibility study on small and medium PWR by utilizing Uranium Silicide Fuel in the aspect of fundamental neturonics, inherent safety, and nonproliferation features International conference

    Natsumi Mitsuboshi, Hiroshi Sagara

    TAMU-INMM Japanese Chapter Workshop, On-line meetin  2022.1 

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  • Am-241 Irradiation Analysis in Experimental Fast Reactor Joyo

    Ame Nucl Society Winter Mtg 2009  2009 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画);(XIV)核拡散抵抗性評価手法の開発

    Alan Takibayev, 相樂 洋, Sidik Permana, Yoshitalia Meiliza, Kairat Ismailov, Vladimir Artisyuk

    日本原子力学会2008年秋の大会予稿集  2008.9 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画);(XII)ATR照射解析

    相樂 洋, 小山真一, 伊藤正彦, 北村了一

    日本原子力学会2008年秋の大会予稿集  2008.9 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画);(XIII)237Np反応度特性の実験的実証

    相樂洋, 桜井 健, 谷 和洋, 岡嶋成晃, 森 貴正

    日本原子力学会2008年秋の大会予稿集  2008.9 

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  • Blanket Fuel with High Proliferation Resistance in Fast Breeder Reactor(III) Theoretical Analysis of Irradiated Sample in JOYO (1)

    sagara, tetsuro yamamoto, Shin-ichi Koyama

    2008.3 

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  • Blanket Fuel with High Proliferation Resistance in FBR (IV)- Protected Pu Production in U-Am Blanket Fuel -

    Yoshitalia Meiliza, Hiroshi SAGARA, Yuichi Sago, Shin-ichi Koyama

    2008.3 

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  • Blanket Fuel with High Proliferation Resistance in Fast Breeder Reactor (I) Grand Design

    Hiroshi SAGARA, Shin-ichi Koyama

    2008.3 

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  • Blanket Fuel with High Proliferation Resistance in Fast Breeder Reactor(III) Theoretical Analysis of Irradiated Sample in JOYO (1)

    2008 

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  • Protected Plutonium Production (P3) and Utilization -Theoretical & Experimental Results for P3, Theoretical Analysis of Irradiation Tests in ATR and JOYO-

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008 

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  • Blanket Fuel with High Proliferation Resistance in Fast Breeder Reactor (I) Grand Design

    2008 

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  • Advanced P3 Reactor Concepts and Denaturing of Plutonium in MOX Fuel

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008 

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  • Protected Plutonium Production (P3) and Utilization -Theoretical & Experimental Results for P3, Theoretical Analysis of Irradiation Tests in ATR and JOYO-

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008 

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  • Studen Session

    Proc Regional Workshop on Managing Nuclear Knowledge  2008 

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発(P3計画);(XI)ATR照射・照射後試験

    日本原子力学会2008年秋の大会予稿集  2008 

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  • Effect of 236U on Protected Plutonium Production International conference

    Hiroshi SAGARA, Tsunetomo Mitsuhashi, kosaku fukuda

    10th International Conference Nuclear Power Safety and Nuclear Education  2007.10 

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    Venue:Obninsk, Russia  

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  • Advanced P3 Reactor Concepts and Denaturing of Plutonium in MOX Fuel

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2008 

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究(II);「常陽」照射Uサンプルの分析(1)

    日本原子力学会2008年春の年会予稿集CD  2008 

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  • Studen Session

    Proc Regional Workshop on Managing Nuclear Knowledge  2008 

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  • Mass Balance of U and TRU in Advanced Fuel Cycle Concepts based on P3 Technology International conference

    K. Fukuda, H. Sagara, M. Ceyhan

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2009.5 

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    Venue:Tokyo, Japan  

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  • Protected Plutonium Breeding in FBR International conference

    Y. Meiliza, H. Sagara

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2009.5 

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    Venue:Tokyo, Japan  

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  • 崩壊熱に基づくプルトニウムの核拡散抵抗性評価

    木村祥紀, 相樂洋

    日本原子力学会2009年春の年会予稿集  2009.3 

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  • Denaturing of Pu by Transmutation of MA during Multy-cycle in Fast Breeder Reactor

    Yoshitalia Meiliza, Hiroshi Sagara

    2009.3 

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  • 高い核拡散抵抗性を有するPu を生成する高速増殖炉の研究;Am 及びCm の効果

    佐合優一, 相樂 洋

    日本原子力学会2009年春の年会予稿集  2009.3 

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  • Effects of MA doping in Fast Breeder Reactor

    GLOBAL 2009  2009 

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  • MCWO-Calculated VVER Annular Fuel Radial Burnup Profile Validation

    Ame. Nucl. Soc. 2009 Annual Mtg.  2009 

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  • Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity - Irradiation Tests of Np and Np-U Samples in Experimental Fast Reactor JOYO (JAEA) and Advanced Thermal Reactor ATR (INL) -

    GLOBAL 2009  2009 

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  • Am-241 Irradiation Analysis in Experimental Fast Reactor Joyo

    Ame Nucl Society Winter Mtg 2009  2009 

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  • Difference in accumulation of curium isotopes formed in 241Am target irradiated in the Japan Material Testing Reactor (JMTR) and an experimental fast reactor (JOYO)

    ACTINIDES 2009  2009 

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  • Denaturing of Pu by Transmutation of MA during Multy-cycle in Fast Breeder Reactor

    2009 

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  • 高い核拡散抵抗性を有するPu を生成する高速炉ブランケット燃料の研究;(VII)サンプルの核変換特性解析(3)

    日本原子力学会2009年春の年会予稿集  2009 

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  • 高速増殖炉におけるPu の改質に関する研究

    日本原子力学会2009年春の年会予稿集  2009 

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  • Effects of MA doping in Fast Breeder Reactor

    GLOBAL 2009  2009 

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  • 高い核拡散抵抗性を有するPu を生成する高速炉ブランケット燃料の研究;(VI)「常陽」照射U サンプルの分析(2)

    日本原子力学会2009年春の年会予稿集  2009 

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  • Mass Balance of U and TRU in Advanced Fuel Cycle Concepts based on P3 Technology

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2009 

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  • Protected Plutonium Breeding in FBR

    2nd Int Sci Technol Forum on Protected Plutonium Utilization Peace and Sustainable Prosperity  2009 

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  • MCWO-Calculated VVER Annular Fuel Radial Burnup Profile Validation

    Ame. Nucl. Soc. 2009 Annual Mtg.  2009 

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  • Protected Plutonium Production by Transmutation of Minor Actinides for Peace and Sustainable Prosperity - Irradiation Tests of Np and Np-U Samples in Experimental Fast Reactor JOYO (JAEA) and Advanced Thermal Reactor ATR (INL) -

    GLOBAL 2009  2009 

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  • Difference in accumulation of curium isotopes formed in 241Am target irradiated in the Japan Material Testing Reactor (JMTR) and an experimental fast reactor (JOYO)

    ACTINIDES 2009  2009 

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  • Development of a Method for the Determination of Spontaneous Fission Nuclides in Irradiated Fuel and Applicability to Pu quantification in Fuel Debris by Dual Time Neutron Measurements International conference

    Taketeru Nagatani, Hiroshi Sagara, Yoshihiro Kosuge, Takayoshi Nohmi, Keisuke Okumura

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Safeguards Approach and Design of Transuranium Fuel Cycle with Accelerator-driven System based on Material Attractiveness International conference

    Akito Oizumi, Hiroshi Sagara

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Development of Passive Neutron Emission Tomography Robust to Its Various Inhibiting Factors and Its Applicability to Nuclear Safeguards International conference

    Katsuyoshi TSUCHIYA, Hiroshi SAGARA, Chi Young HAN

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Measurement System Requirements for Photofission Signal Detection with Coincidence Neutron Counting Method International conference

    Kim Wei Chin, Hiroshi Sagara, Jun-ichi Hori, Yoshiyuki Takahashi

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Once-through High Burnup Fuel Management Strategy with Dual Neutron Energy Spectrum Core in HTGR International conference

    Hong Fatt Chong, Hiroshi Sagara

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Neutronics and Non-proliferation features of Accelerator-Driven System using TRU fuelwith separation resistance of an actinide element

    S Yamaguchi, Akito Ohizumi, Hiroshi SAGARA

    AESJ Spring Meeting 2022  2022.3 

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  • Evaluation for Proliferation Resistance of small and medium modular LWR with U3Si2 fuel International conference

    Natsumi Mitsuboshi, Hiroshi Sagara

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (2) Performance of the Device in Reactivity Control and Nuclear Material Management International conference

    Hiroshi Sagara, Masatoshi Kawashima, Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (1) Current Status of Overall Project Progress International conference

    Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashim

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • 東京工業大学における核セキュリティ教育

    相樂洋

    日本核物質管理学会第8回研究会  2022.6 

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  • Safety and proliferation resistance of small and medium-sized sodium-cooled fast reactors with passive shutdown devices

    Haruka Okazaki, Masatoshi Kawashima, Hiroshi Sagara

    International Symposium on Zero-Carbon Energy Systems  2023.1 

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  • MA核変換を利用したPuの改質に関する研究(IV) –マスバランスの予備評価-

    相樂 洋, 齊藤 正樹

    日本原子力学会秋の年会2005  2005.9 

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  • Transmutation of Sn-126 Using Spallation Reaction

    日本原子力学会2007年春の年会予稿CD  2007 

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  • Sn-126 Transmutation in Spallation Target of ADS

    ANS/ENS International Meeting  2007 

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  • Protected Plutonium Production in Fast Breeder Reactor 窶鄭ttractiveness of Plutonium-

    ANS/ENS International Meeting  2007 

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  • Sn-126 Transmutation in Spallation Target of ADS

    ANS/ENS International Meeting  2007 

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  • Protected Plutonium Production in Fast Breeder Reactor 窶鄭ttractiveness of Plutonium-

    ANS/ENS International Meeting  2007 

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  • Prospects of Inventories of U, Pu and MAs and Mass Balance in PPP Cycle

    onsultancy on technical issues related to Protected Plutonium Utilization  2006 

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  • Prospects of Inventories of U, Pu and MAs and Mass Balance in PPP Cycle

    onsultancy on technical issues related to Protected Plutonium Utilization  2006 

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  • Impact of Uranium-silicide fuels on simultaneous enhancement of nuclear safety-security features and fuel lifetime extension in large scale LWRs International conference

    Mori Yusuke, Sagara Hiroshi, Chong Hong Fatt

    International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES)  2025.1 

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  • Denaturing of Plutonium by Transmutation of Minor Actinide International conference

    Hiroshi SAGARA, Masaki SAITO

    COE Satellite Technical Meeting on Non-proliferation and Protected Plutonium Production (P3)  2006.12 

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    Venue:Tokyo Institute of Technology, Japan  

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  • Denaturing of Plutonium by Transmutation of MA (VI) Fusion Neutron Source

    Alan Takibayev, Masaki Saito, Hiroshi Sagara

    日本原子力学会秋の年会2005  2005.9 

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    Venue:八戸工業大学  

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  • Denaturing of Plutonium by Transmutation of Minor Actinide

    IAEA Consultancy Meeting on Technical Issues related to Protected Plutonium Utilization  2006 

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  • MA核変換を利用したPuの改質に関する研究(V) 加速器駆動システムによる軍事用プルトニウムの改質

    齊藤正樹, 日高一誠, 相樂 洋

    日本原子力学会秋の年会2005  2005.9 

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    Venue:八戸工業大学  

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  • Reducing the Proliferation Risk of Utilizing HALEU Fuel in Sodium-Cooled Fast Reactors

    Eva M. Lisowski, Hiroshi Sagara

    AESJ 2024 Annual Mtg  2024.3 

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    Language:English   Presentation type:Oral presentation (general)  

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  • Protected Plutonium Production by Doping MA in Blanket Region of Fast Breeder Reactor Effect of ZrH2

    Yoshitalia Meliza, Hiroshi Sagara, Masaki Saito

    日本原子力学会秋の年会2005  2005.9 

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    Language:English   Presentation type:Poster presentation  

    Venue:八戸工業大学  

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Industrial property rights

  • 炉心損傷防止構造体及びそれを備えた原子炉炉心

    相樂洋, 川島 正俊, 守田 幸路

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    Applicant:国立大学法人東京工業大学

    Application no:特願2022-060578  Date applied:2022.3

    Announcement no:特開2023-151133  Date announced:2023.10

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  • 原子炉施設および原子炉施設の監視方法

    相樂洋, 千葉敏, 木村 礼, 宮寺 晴夫, 杉田 宰

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    Applicant:国立大学法人東京工業大学, 東芝エネルギーシステムズ株式会社

    Application no:特願2018-186642  Date applied:2018.10

    Announcement no:特開2020-056652  Date announced:2020.4

    Patent/Registration no:特許第7140621号  Date registered:2022.9 

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Works

  • Research on the Fast Breeder Reactor Blanket Fuel with High Proliferation Resistance

    2007 - 2009

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    Work type:Artistic work  

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  • 将来高速炉システムに関する調査・検討

    2007 - 2009

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    Work type:Artistic work  

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  • 高い核拡散抵抗性を有するPuを生成する高速炉ブランケット燃料の研究

    2007 - 2009

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    Work type:Artistic work  

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  • Research and Surveys on the Future Fast Reactor System (III)

    2007 - 2009

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    Work type:Artistic work  

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  • Development of Innovative Nuclear Reactor Technology to Produce Protected Plutonium with High Proliferation Resistance

    2005 - 2009

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    Work type:Artistic work  

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  • 強い核拡散抵抗性を有するPuを生成する革新的原子炉技術開発

    2005 - 2009

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    Work type:Artistic work  

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Awards

  • 東工大工系教育賞 特別賞

    2023.5   東京工業大学 工系3学院  

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  • Award to Outstanding Reviewer, Nuclear Engine ering and Technology

    2022.12   Korean Nuclear Society  

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  • Best Paper Award, the 43rd Annual Meeting of the Institute of Nuclear Materials Management Japan Chapter

    2022.11   Institute of Nuclear Material Management Japan Chapter  

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  • 令和元年度 東工大教育賞

    2020.4   東京工業大学  

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  • The 47th Best Article Award, Atomic Energy Society Japan

    2015.3   Atomic Energy Society Japan  

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  • U.S. DOE Fellowship Program Award

    2008  

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  • World Nuclear University Fellow in the 2006 WNU Summer Institute

    2006.8   World Nuclear University  

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  • 財団法人理工学振興会 平成17年度研究助成

    2006.1   財団法人 理工学振興会  

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    Country:Japan

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  • Best Presentation Award in COE-INES Captainship Educational Program

    2005.12   COE-INES  

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Research Projects

  • Development of non-destructive assay technique for nuclear material detection and enrichment estimation by photo-nuclear reaction with bremsstrahlung X-ray

    Grant number:25K01706  2025.4 - 2029.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research (B)

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    Grant amount:\25870000 ( Direct Cost: \19900000 、 Indirect Cost:\5970000 )

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  • 低エネルギー陽子入射反応からの高エネルギーガンマ線を用いた核物質検知技術の開発

    Grant number:23K26587  2023.4 - 2027.3

    日本学術振興会  科学研究費助成事業  基盤研究(B)

    片渕 竜也, 石塚 知香子, 相楽 洋, 田辺 鴻典

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    Grant amount:\18720000 ( Direct Cost: \14400000 、 Indirect Cost:\4320000 )

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  • フィジカル・サイバー空間にまたがる原子力プラント 3S を俯瞰し実践・主導する規制人材育成

    2022 - 2026

    その他 

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  • 高安全・核セキュリティ及び低廃棄物処分負荷を同時達成する中小型軽水炉に関する研究

    2022 - 2023

    企業からの受託研究 

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  • 照射済燃料の核鑑識シグネチャ核種に関する研究

    2020 - 2021

    国内共同研究 

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  • 高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 <再委託:炉心開発>

    2019 - 2022

    Sponsored Research Program (Governmental)  エネルギー対策特別会計委託事業(原子力システム研究開発事業)

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  • 廃棄物処分の環境影響を基点とした原子力システム研究

    2019 - 2022

    出資金による受託研究 

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  • 中性子・ガンマ線計測を用いた非破壊測定技術に関する研究

    2019 - 2021

    国内共同研究 

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  • 超小型原子炉の核セキュリティ・保障措置に係る課題検討および実験データからの核データ構築に係る予備検討

    2019

    Sponsored Research Program  社会的要請に応える革新な原子力技術開発支援事業

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  • 溶融塩炉の核データ、炉心熱水力及びプラント動特性・安全性、核拡散抵抗性に関する研究

    2019

    出資金による受託研究 

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  • Nuclear data analysis important for non-destructive assay techniques development required for non-proliferation and prevention of nuclear terrorism

    Grant number:17K07005  2017 - 2020

    Japan Society for the Promotion of Science  Commisioned research by the investment  Grant-in-Aid for Scientific Research (C)

    Sagara Hiroshi

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    Grant amount:\4810000 ( Direct Cost: \3700000 、 Indirect Cost:\1110000 )

    There are strong needs of nuclear reaction and its nuclear data accuracy different from conventional nuclear engineering or radiation application, from the aspects of nuclear non-proliferation and security. In this research, nuclear reactions of nuclear material in active/passive measurement by non-destructive assay (NDA) technology were focused, and the accuracy of nuclear data important to NDA measurement were summarized. Passive/active neutron measurement, passive gamma/neutron tomography, active method utilizing photo-nuclear reaction were investigated and analyzed. As an advanced point, some of measurement were proceeded for the future nuclear data measurements.

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  • Assessment of TRU mass balance and nonproliferation by using FAMILY-21 calculation code based on the prediction of nuclear power facility utilization in Japan

    2017 - 2018

    Domestic joint research within Japan 

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  • 福島第一原子力発電所の燃料デブリ計量管理技術開発に資する非破壊測定の高度化

    2017

    出資金による受託研究 

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  • Quantifying the features of safety and non-proliferation of high temperature gas cooled reactors

    2015 - 2017

    Domestic joint research within Japan 

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  • ガンマ線測定を用いた廃棄物管理手法に関する研究開発

    2015

    Sponsored Research Program (Governmental) 

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  • 随伴FPガンマ線測定法を用いた燃料デブリ内核物質量の非破壊測定手法の研究開発

    2013 - 2014

    Sponsored Research Program (Governmental) 

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  • Research on the Fast Breeder Reactor Blanket Fuel with High Proliferation Resistance

    2007 - 2009

    Domestic joint research within Japan 

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  • Research and Surveys on the Future Fast Reactor System (III)

    2007 - 2009

    Domestic joint research within Japan 

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  • 原子力システムの核拡散抵抗性の評価手法開発

    2006

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    Grant type:Competitive

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  • Development of the Evaluation Methodology of Proliferation Resistance of Nuclear System

    2006

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    Grant type:Competitive

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  • Development of Innovative Nuclear Reactor Technology to Produce Protected Plutonium with High Proliferation Resistance

    2005 - 2009

    Commisioned research by the investment 

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