Details of the Researcher

PHOTO

Hiroki Shishido
Section
Graduate School of Engineering
Job title
Assistant Professor
Degree

  • 博士（工学）（東北大学）

  • 修士（工学）（東北大学）

e-Rad No.
90827792

Professional Memberships 4

  • The Electrochemical Society of Japan

    - Present

  • Molten Salt Committee

    - Present

  • The Japan Society of Plasma Science and Nuclear Fusion Research

    - Present

  • ATOMIC ENERGY SOCIETY OF JAPAN

    - Present

Awards 1

  1. 第7回日本原子力学会新型炉部会部会賞 優秀講演賞

    2025/03　一般社団法人 日本原子力学会 新型炉部会　MHD電解フィルタ開発に向けたフッ化物溶融塩中における溶存水の挙動評価

Papers 17

  1. Introduction of Fusion Reactors as Transmutation Systems for Minor Actinides and Fission Products Peer-reviewed

    Hiroki Shishido, Hidetoshi Hashizume

    Nuclear Technology　2025

    DOI： 10.1080/00295450.2025.2472556 　

  2. Numerical prediction of the heat transfer properties of Flinabe molten salt as a coolant in a nuclear system Peer-reviewed

    Hiroki Shishido, Noritaka Yusa, Hidetoshi Hashizume, Yoshiki Ishii, Norikazu Ohtori

    Annals of Nuclear Energy　206　110631-110631　2024/10

    Publisher: Elsevier BV

    DOI： 10.1016/j.anucene.2024.110631 　

    ISSN： 0306-4549

  3. Numerical analysis of the viscosity of ZrF4–BeF2 molten salts for nuclear transmutation using fusion neutron sources Peer-reviewed

    Hiroki Shishido, Hidetoshi Hashizume

    Fusion Engineering and Design　203　114456-114456　2024/06

    Publisher: Elsevier BV

    DOI： 10.1016/j.fusengdes.2024.114456 　

    ISSN： 0920-3796

  4. Introduction of Fusion Reactor as Transmutation System for Minor Actinides and Fission Product Peer-reviewed

    Hidetoshi Hashizume, Hiroki Shishido

    2024 International Congress on Advances in Nuclear Power Plants (ICAPP)　19-28　2024

    Publisher: American Nuclear Society

    DOI： 10.13182/t130-44212 　

  5. Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor Peer-reviewed

    Masaki Shimizu, Hiroki Shishido, Hidetoshi Hashizume

    Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics　V002T05A014　2021/08/04

    Publisher: American Society of Mechanical Engineers

    DOI： 10.1115/icone28-65139 　

    More details Close

    Abstract This study proposes to make effective use of plutonium transmuted from minor actinides (MA) by fusion reactors as fertile fuel in a light water reactor (LWR). The plutonium transmuted from MA, particularly Pu-238, has a large neutron capture cross section and becomes fissile Pu-239 by the reaction. If the plutonium transmuted from MA is loaded into LWR appropriately, there is a possibility to maintain a constant effective multiplication factor. This study evaluated the effects of the plutonium transmuted from MA on a full MOX boiled water reactor (BWR) core by Monte Carlo-based neutron transport and burnup calculation. We revealed that some fuel assemblies achieved the effective multiplication factor is greater than 1.0 and its decrease was significantly small (−0.013) during 400 days operation. However, under this condition, the power peaking factor was 1.4, which should be unacceptable from the viewpoint of thermal design. Inventories of heavy nuclides in fuel cycles was evaluated using a simple diagram and its result indicated that the accumulation of MA in the fuel cycle was reduced by introducing the MA transmutation and the Pu recycle system. Furthermore, the amount of MA production and MA transmutation are balanced by introducing two fusion reactors with 3 GW thermal output into the fuel cycle, and the MA inventory was equilibrated.

  6. Evaluation of Neutronic and Thermophysical Characteristics of Molten Salts Specialized for Long-Lived Fission Products Transmutation in a Fusion Reactor Peer-reviewed

    Taku KITASAKA, Hiroki SHISHIDO, Hidetoshi HASHIZUME

    Plasma and Fusion Research　15　2405077-2405077　2020/11/04

    Publisher: Japan Society of Plasma Science and Nuclear Fusion Research

    DOI： 10.1585/pfr.15.2405077 　

    eISSN： 1880-6821

  7. Construction of minor actinides reduction scenario in Japan utilizing fusion reactors

    Yuki Furudate, Hiroki Shishido, Noritaka Yusa, Hidetoshi Hashizume

    Progress in Nuclear Energy　103　28-32　2018/03

    Publisher: Elsevier BV

    DOI： 10.1016/j.pnucene.2017.11.003 　

    ISSN： 0149-1970

  8. Anomalous excess heat generated by the interaction between nano-structured Pd/Ni surface and D2 gas Peer-reviewed

    Takehiko Ito, Yasuhiro Iwamura, Jirohta Kasagi, Hiroki Shishido

    Journal of Condensed Matter Nuclear Science　24　179-190　2017

    ISSN： 2227-3123

  9. Thermal Design Investigation for a Flinabe Blanket System Peer-reviewed

    Hiroki Shishido, Noritaka Yusa, Hidetoshi Hashizume, Yoshiki Ishii, Norikazu Ohtori

    FUSION SCIENCE AND TECHNOLOGY　72　(3)　382-388　2017

    DOI： 10.1080/15361055.2017.1330623 　

    ISSN： 1536-1055

    eISSN： 1943-7641

  10. Discussion on the effect of NaF on physical properties of Flinabe in comparison to Flibe from molecular dynamics simulations Peer-reviewed

    H. Shishido, N. Yusa, H. Hashizume, Y. Ishii, N. Ohtori

    25th International TOKI Conference (ITC-24), Toki, Japan　2015/11/03

  11. EVALUATION OF PHYSICAL PROPERTIES OF THE MOLTEN SALT MIXTURES FLINABE FOR A FUSION BLANKET SYSTEM USING MOLECULAR DYNAMICS SIMULATION Peer-reviewed

    Hiroki Shishido, Noritaka Yusa, Hidetoshi Hashizume, Yoshiki Ishii, Norikazu Ohtori

    FUSION SCIENCE AND TECHNOLOGY　68　(3)　669-673　2015/10

    DOI： 10.13182/FST14-975 　

    ISSN： 1536-1055

    eISSN： 1943-7641

  12. Designing of a fusion blanket system using molten salt flinabe for transmutation of minor actinides Peer-reviewed

    H. Shishido, Y. Furudate, N. Yusa, H. Hashizume

    GLOBAL2015, Paris, France　2015/09/20

  13. Evaluation of neutronic performance of Flibe+LiI molten salt blanket system for MA transmutation Peer-reviewed

    Y. Furudate, H. Shishido, N. Yusa, H. Hashizume

    The 17th International Symposium on Applied Electromagnetics and Mechanics, Kobe, Japan　2015/09/15

  14. Numerical investigation of the ill-posedness of inverse problems to size a crack from eddy current signals Peer-reviewed

    Noritaka Yusa, Hiroki Shishido, Hidetoshi Hashizume

    The 2nd International Conference on Maintenance Science and Technology　2014/11/02

  15. Development of electromagnetic non-destructive testing method for the inspection of heat exchanger tubes of Japan Sodium-Cooled Fast Reactor –Part I Application of remote field eddy current testing

    Noritaka Yusa, Hiroki Shishido, Hidetoshi Hashizume

    The 19th International Workshop on Electromagnetic Nondestructive Evaluation, Xi’an, China　2014/06/25

  16. Evaluating the III-posedness of inverse problem to size flaws from eddy current NDT signals obtained with an absolute type probe Peer-reviewed

    Noritaka Yusa, Hiroki Shishido, Hidetoshi Hashizume

    Applied Mechanics and Materials　619　337-341　2014

    Publisher: Trans Tech Publications Ltd

    DOI： 10.4028/www.scientific.net/AMM.619.337 　

    ISSN： 1662-7482 1660-9336

  17. PROPOSAL OF A NOVEL BLANKET SYSTEM USING LiF-BeF2-LiI FOR A FUSION REACTOR Peer-reviewed

    Hiroki Shishido, Youngmin Han, Kentaro Matsui, Noritaka Yusa, Hidetoshi Hashizume

    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 5　5　V005T14A012　2014

Show all ︎Show first 5

Misc. 2

  1. 放射性廃棄物の核変換処理を目的とした核融合炉溶融塩ブランケット成立性検討(2)分子動力学法を用いたFlinabeの熱物性評価

    宍戸博紀, 古館佑樹, 遊佐訓孝, 橋爪秀利, 石井良樹, 大鳥範和

    日本原子力学会春の年会予稿集(CD-ROM)　2016　ROMBUNNO.1J13　2016/03/16

  2. B224 Time-dependent Neutronic Analysis for Transformation of FLiNaBe in a Fusion Blanket System

    SHISHIDO Hiroki, FURUDATE Yuki, YUSA Noritaka, HASHIZUME Hidetoshi

    National Symposium on Power and Energy Systems　2014　(19)　255-256　2014/06/25

    Publisher: The Japan Society of Mechanical Engineers

    More details Close

    This study evaluates nuclear characteristics of molten salt, namely LiF-NaF-BeF_2 (FLiNaBe), from the viewpoint of its application to a liquid blanket system in a fusion reactor. Monte Carlo numerical simulations using MVP-2.0 with JENDL-4.0 data library and time-dependent nuclear transmutation analysis are carried out to evaluate tritium breeding ratio, change in the compositions of the molten salt. Induced radioactivity of Na contained in FLiNaBe is also evaluated. The results of the numerical analysis reveal that the thermophysical properties of FLiNaBe should vary because the compositions of the molten salt definitely change due to the fusion plasma neutron during power plant operation.

Presentations 1

  1. A Dynamic Model of the Sustainable Twin Nuclear Fuel Cycle by Introducing Fusion Transmutation Reactors International-presentation

    Hiroki Shishido

    The 27th International Toki Conference on Plasma Fusion Research & The 13th Asia Pacific Plasma Theory Conference　2018/11/19

Research Projects 8

  1. 制約のない磁場配位が可能な分割型高温超伝導マグネットにおける接合現象の多角的理解

    伊藤 悟

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 基盤研究(B)

    Institution: 東北大学

    2025/04 - 2028/03

  2. 磁場を与えるだけで運転中の溶融塩から不純物を除去するMHD電解フィルタの創出

    宍戸 博紀

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 若手研究

    Institution: 東北大学

    2024/04/01 - 2027/03/31

  3. Development of 4-phase continuous diverter system by MHD controlling

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (A)

    Institution: Tohoku University

    2021/04 - 2026/03

  4. 高い安全性を有する放射性廃棄物ゼロエミッション溶融塩炉原子力システム実現への挑戦

    相澤 直人, 宍戸 博紀

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 基盤研究(C)

    Institution: 東北大学

    2022/04/01 - 2025/03/31

    More details Close

    本研究では、原子力プラントで発生する放射性核種を同一プラント内ですべて核変換し、放射性廃棄物の排出を極小とする自己完結的な高い安全性を有する原子力システムの実現を目標として、運転中に燃料塩の調整・生成元素の連続除去が可能な溶融塩炉原子炉システムを対象に2022年度は以下の検討を行った。 １．溶融塩炉原子炉システムの設計を行うにあたり、炉心核設計のための解析環境の整備ならびに溶融塩物性解析のための解析ツールの整備を行った。また、溶融塩組成の検討にあたり、溶融塩に溶かすための元素特性の基礎検討を開始した。 ２．溶融塩炉炉心の核設計として、過去に米国オークリッジ国立研究所にて建設および運転経験のあるフッ化物溶融塩実験炉MSREの炉心を元に、ウラン燃料溶融塩および黒鉛減速材ブロックを用いた無限燃料セル体系を用いて、これまでに溶融塩炉における核変換研究が行われてこなかった長寿命核分裂生成物(LLFP)を対象として、溶融塩炉の運転中において生成したLLFPが自己完結的に核変換可能かどうか検討を行った。その結果、黒鉛減速材ブロック中にLLFPの核変換のための専用流路を設けた燃料セル設計において、専用流路の大きさを変更することによって運転中のLLFP生成量と同量もしくは生成量を上回るLLFP核変換が実現可能であることが示された。また、LLFP核変換用専用流路の導入によって低下する反応度についても、ウラン濃縮度を増加させることによって補償可能であることが示された。

  5. Elucidation of chemical stability and interaction of waste elements for the creation of liquid transmutation targets

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Early-Career Scientists

    Institution: Tohoku University

    2021/04 - 2024/03

  6. Detailed analysis of joining characteristics and establishment of maintenance scenario for remountable high temperature superconducting magnet under irradiation environment

    Ito Satoshi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Scientific Research (B)

    Institution: Tohoku University

    2020/04/01 - 2023/03/31

    More details Close

    For consideration of construction, operation and maintenance of segmented high-temperature superconducting (HTS) fusion magnets, we carried out 1) Detailed evaluation of REBCO tape and joint characteristics under high magnetic field and irradiation environment, 2) Fabrication of superconducting quench detectors for high field and clarification of factors affecting quench detection, and 3) Consideration of design and maintenance of the segmented HTS magnets taking into account high field and irradiation environments. In 1), we obtained temperature and magnetic field dependence of the interface resistance inside the REBCO tape, and the critical current characteristics of the REBCO tape with proton irradiation at liquid nitrogen temperature. In 2), we demonstrated the quench detection of various REBCO coils using the Nb-Ti quench detector and developed the Nb3Al quench detector. In 3), we evaluated the effects of magnetic field and irradiation on magnet design.

  7. Proposal of the innovative fusion reactor for nuclear transmutation by the utilization of a super fast neutron and the high-level radioactive waste

    Hashizume Hidetoshi

    Offer Organization: Japan Society for the Promotion of Science

    System: Grants-in-Aid for Scientific Research

    Category: Grant-in-Aid for Challenging Research (Pioneering)

    Institution: Tohoku University

    2017/06 - 2020/03

    More details Close

    We have proposed a completely new concept of a fusion reactor that combines ultra-high-energy 14 MeV neutrons generated by fusion reactions with high-level waste (fission products and minor actinides) contained in spent nuclear fuel produced by nuclear power plants. We have performed designing of the minor actinide fuel and transmutation system, and also the blanket including the fission products transmutation system. We have indicated successful scenarios that it is possible to surely reduce the domestic storage amount of these high-level wastes by introducing the innovative fusion reactors to Japan.

  8. 自己発熱機能を有する新型溶融塩ブランケットシステムの開発

    宍戸 博紀

    Offer Organization: 日本学術振興会

    System: 科学研究費助成事業

    Category: 特別研究員奨励費

    Institution: 東北大学

    2015/04 - 2018/03

    More details Close

    本研究は、Flibe (LiF-BeF2) およびFlinabe (LiF-NaF-BeF2) などの既存溶融塩に対し、重元素を添加した自己発熱機能を有する高性能新型溶融塩の開発、およびその溶融塩を用いたブランケットシステムの設計最適化を目指す。 昨年度Flinabeにおいても熱物性改善が必要であると結論付けられたことから、異なる物質を添加した場合の熱物性評価を実施した。自己発熱性を発現させる添加候補としてCsFを考え、FlibeにCsFを添加した三元系溶融塩の熱物性（比熱、粘性、熱伝導率）について数値解析評価した。CsF添加量が小の場合、熱物性は元のFlibeから大きく変化しない。しかし、CsFの質量が大であることから、CsF比増大に伴い熱伝導率が著しく減少してしまうことが明らかとなった。以上から、Flibe+CsFのFlinabeに対する優位性は見られなかった。ただし、FlibeにCsFを少量添加した場合、融点が最大で約40 K減少することがこれまでの実験により明らかとなっている。よって、Flinabeに対し少量のCsFを添加することで、Flinabeの熱物性を大きく変えることなく、融点のみが減少する可能性が考えられる。 また、溶融塩を簡便かつ大量に精製できる手法確立を目的として、一方向凝固法の適用性を評価した。昨年度のFlinakに引き続き、本年度はFlibeを対象とした。その結果、主にBeF2に含まれている黒色の不純物が試料上部に偏析する様子を観測した。また、ICP-MSにより金属不純物量を分析したところ、不純物の中でも特に多く含まれる鉄元素が試料上部に有意に偏析するという結果が得られている。さらに本手法は偏析現象を利用しているため、組成を適当に配合したとしても、試験後には自動的に共晶組成に調整されるという利点もあり、溶融塩精製の際に極めて有効な手法であると考えられる。

Show all Show first 5