Yamamoto A, Endo T, Takeda S, Koike H, Yamaji K, Asano K. Deterministic Transport Calculation Method for Statistical Geometry with Small Fuel Particles. Nuclear Science and Engineering. 2024. 198. 5. 981-992
Katano R, Oizumi A, Fukushima M, Pyeon C.H, Yamamoto A, Endo T. Impact of Uncertainty Reduction on Lead-Bismuth Coolant in Accelerator-Driven System Using Sample Reactivity Experiments. Nuclear Science and Engineering. 2024. 198. 6. 1215-1234
Maruyama S, Endo T, Yamamoto A. Uncertainty reduction of sodium void reactivity using data from a sodium shielding experiment. Journal of Nuclear Science and Technology. 2024. 61. 1. 31-43
Yamamoto A, Endo T. Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel. Journal of Nuclear Science and Technology. 2024. 61. 3. 354-362
Yamamoto A, Endo T. Application of Equivalent Dancoff Factor Method for Resonance Calculation of Double Heterogeneous Fuel. Transactions of the American Nuclear Society. 2023. 128. 1. 690-693
Tada K, Yamamoto A, Endo T, Chiba G, Ono M, Tojo M. Development of Nuclear Data Processing Code FRENDY Version 2. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. 2022. 107-116
Katano R, Yamamoto A, Endo T. Proposal and Application of ROM-Lasso Method for Sensitivity Coefficient Evaluation. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. 2022. 2032-2041
Yamamoto A, Endo T, Takeda S, Koike H, Yamaji K, Ieyama K, Asano K. A New Approach for Resonance Treatment of Doubly Heterogeneous Fuel using the RSE method. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. 2022. 2042-2051
Endo T, Nishioka F, Yamamoto A, Yamanaka M, Pyeon C.H. AREA RATIO METHOD USING DYNAMIC MODE DECOMPOSITION. Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. 2022. 3366-3375
Verification of Neutronics Analysis Method Using CBZ and GENESIS for a Prismatic High-Temperature Gas-Cooled Reactor
(International Conference on Physics of Reactors 2024 2024)
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation
(International Conference on Physics of Reactors 2024 2024)