論文

• Eva M. Lisowski, Hiroshi Sagara. Increased 238Pu Production in Proliferation-Resistant U-10Zr Fuel Produced from Reprocessed Uranium Containing Unseparated 237Np, Nuclear Technology, Vol. 211, Issue 8, Jan. 2025.

国内会議発表 (査読有り)

• 寺山 正太郎, 相樂 洋, LISOWSKI EVAMORGAN. 運転中の燃料交換が可能なナトリウム冷却高速炉のSafeguards by designに関する研究, 日本核物質管理学会第45回年次大会, 日本核物質管理学会第45回年次大会論文集, Nov. 2024.
• Eva Lisowski, Hiroshi Sagara. Neutronics and Proliferation Resistance Assessment of U-10Zr Fuel Containing Unseparated Np-237, 45th Annual Mtg. INMMJ, Proc. 45th Annual Mtg. INMMJ, Nov. 2024.
• Lisowski Eva, Hiroshi Sagara. Material and Facility Attractiveness to Non-Peaceful Actors of HALEU Fuel Utilization in Sodium-Cooled Fast Reactor Fuel Cycles (2)19.9-HALEU Fuel Material Attractiveness, Proc. 44th Annual Mtg. INMMJ, Nov. 2023.
• Eva Lisowski, Hiroshi Sagara. Evaluating the Material and Facility Attractiveness in Sodium-Cooled Fast Reactor Fuel Cycles to Enhance Proliferation Resistance (1) HALEU Fuel Evaluation Research Planning, Proc. the 43rd Annual Meeting of the Institute of Nuclear Materials Management Japan Chapter, Nov. 2022.

国際会議発表 (査読なし・不明)

• Shotaro Terayama, Hiroshi Sagara, Lisowski Eva. Safeguards by design of sodium-cooled fast reactor with online re-fueling function, International Symposium on Green Transformation Initiative and Innovative Zero-Carbon Energy Systems(GXI-ZES), 2025.

国内会議発表 (査読なし・不明)

• 寺山 正太郎, 相樂 洋, LISOWSKI EVAMORGAN. 運転中の燃料交換が可能なナトリウム冷却高速炉のSafeguards by design に関する研究, 日本原子力学会2025年春の年会, Mar. 2025.
• Eva M. Lisowski, Hiroshi Sagara. Reducing the Proliferation Risk of Utilizing HALEU Fuel in Sodium-Cooled Fast Reactors, AESJ 2024 Annual Mtg, Mar. 2024.

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