Journal Paper

• Kodai Fukuda, Toru Obara, Kenya Suyama. Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor, Nuclear Technology, published online, July 2024.
• Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara. Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy, Nuclear Science and Engineering, published online, May 2024.
• Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara. Small rotational fuel-shuffling breed-and-burn sodium-cooled and nitride-fueled fast reactor with LBE reflectors, Annals of Nuclear Energy, Vol. 201, 110445, Mar. 2024.

International Conference (Reviewed)

• Alexandru Catalin Stafie, Toru Obara. Plutonium vector analysis for optimizing the RFBB strategy applied for a nitride fuel, lead-cooled fast reactor, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 1C-01-01, Oct. 2024.
• Xucheng Zhao, Toru Obara. Replication of CANDLE Burning Wave in Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 1C-01-03, Oct. 2024.
• T. Obara, N. Horiike. Fuel Cycle Features of Sodium-Cooled Metal Fuel RFBBs, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 3C-01-03, Oct. 2024.
• Xucheng Zhao, Toru Obara. Feasibility of Innovative Lead-Bismuth-cooled Fast Reactor Core Design Using Metallic Fuel, Global Symposium on Lead and Lead Alloy Cooled Nuclear Energy Science and Technology 2024 (GLANST 2024), Sept. 2024.

Domestic Conference (Not reviewed / Unknown)

• Toru OBARA, Sambuu Odmaa. Burnup Characteristics of Silicide Fueled RFBB with Sodium Coolant, 2024 autumn meeting of Atomic Energy Society of Japan, Proc. of 2024 autumn meeting of Atomic Energy Society of Japan, 1G10, Sept. 2024.
• Ken KUROSAKI, Tamotsu KOZAKI, Genichiro WAKABAYASHI, Toru OBARA. Issues and correspondence in the Global Nuclear Human Resource Development Initiative Project (5) Nuclear Open Campus, 2024 autumn meeting of Atomic Energy Society of Japan, Proc. of 2024 autumn meeting of Atomic Energy Society of Japan, 1L_PL05, Sept. 2024.
• Ren Horikoshi, Toru OBARA. Start Up Core characteristics of Lead-cooled RFBB with Nitride Fuel, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 3L13, Mar. 2024.
• Naoki Horiike, Toru OBARA. Core Characteristics of Sodium Cooled RFBB with Metal Fuel, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 3L12, Mar. 2024.
• Hiroki Takezawa, Toru OBARA. Improvement of fuel debris criticality analysis technology using non-contact measurement method (6) Preliminary verification of a criticality impact analysis method using a fast-thermal weakly coupled reactor system, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 2L17, Mar. 2024.
• Seiya Manabe, Jun Nishiyama, Hideki Harano, Toru OBARA. Improvement of fuel debris criticality analysis technology using non-contact measurement method (5) Performance Evaluation for a Fuel Debris Criticality Characterization System Using Active Neutron Method, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 2L16, Mar. 2024.
• Jun Nishiyama, Seiya Manabe, Hideki Harano, Toru OBARA. Improvement of fuel debris criticality analysis technology using non-contact measurement method (4) Evaluation of the fuel debris criticality characteristics by using measurement system with active neutron method, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 2L15, Mar. 2024.
• Xiaoqing Huang, Toru Obara. Feasibility of silicide fueled RFBB using lead coolant, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 3L11, Mar. 2024.

Other Publication

• Toru OBARA. 小型モジュール炉開発の現状と展望, 化学工学, 化学工学会, Vol. 88, No. 5, pp. 207-210, May 2024.

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