Articles

H. Tanaka, T. Narukawa, T. Takata, Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident, Journal of Nuclear Engineering, Vol. 6, No. 1, 6 10.3390/jne6010006 (2025). (selected as an issue cover)

Y. Tasaki, T. Narukawa, Y. Udagawa, Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions, Journal of Nuclear Science and Technology, Vol. 61, No. 10, pp. 1349–1359, 10.1080/00223131.2024.2321342 (2024).

F. Li, T. Narukawa, Y. Udagawa, The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding, Journal of Nuclear Science and Technology, Vol. 61, No. 8, pp. 1036–1047, 10.1080/00223131.2023.2293100 (2023).

T. Narukawa, K. Kondo, Y. Fujimura, K. Kakiuchi, Y. Udagawa, Y. Nemoto, Oxidation and embrittlement behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions, Journal of Nuclear Materials, Vol. 587, 154736, 10.1016/j.jnucmat.2023.154736 (2023).

A. Uchibori, N. Doda, M. Aoyagi, M. Sonehara, J. Sogabe, Y. Okano, T. Takata, M. Tanaka, Y. Enuma, T. Wakai, T. Asayama, H. Ohshima, Numerical simulation technologies for safety evaluation in plant lifecycle optimization method, ARKADIA for advanced reactors, Nuclear Engineering and Design, Vol. 413, 112492, 10.1016/j.nucengdes.2023.112492 (2023).

T. Narukawa, S. Hamaguchi, T. Takata, Y. Udagawa, Hierarchical Bayesian modeling to quantify fracture limit uncertainty of high-burnup advanced fuel cladding tubes under loss-of-coolant accident conditions, Nuclear Engineering and Design, Vol. 411, 112443, 10.1016/j.nucengdes.2023.112443 (2023).

T. Narukawa, K. Kondo, Y. Fujimura, K. Kakiuchi, Y. Udagawa, Y. Nemoto, Behavior of FeCrAl-ODS cladding tube under loss-of-coolant accident conditions, Journal of Nuclear Materials, Vol. 582, 154467, 10.1016/j.jnucmat.2023.154467 (2023).

D. L.Y. Louie, M. Aoyagi, A. Uchibori, T. Takata, D. L. Luxat, Validation study of sodium pool fire modeling efforts in MELCOR and SPHINCS codes, Nuclear Engineering and Design, Vol. 407, 112285, 10.1016/j.nucengdes.2023.112285 (2023).

廣川直機, 山口彰, 高田孝, 成川隆文, 公衆リスク低減のための格納容器ベント実施判断基準と防護措置に関する評価手法の検討, 日本原子力学会和文論文誌, Vol. 22, No. 1, p. 25-37, 10.3327/taesj.J22.003 (2023).

廣川直機, 山口彰, 高田孝, 張承賢, 格納容器ベントにおけるSTAMP/STPAを用いた定性的システムリスク分析, 日本原子力学会和文論文誌, Vol. 21, No. 4, p. 183-200, 10.3327/taesj.J21.018 (2022).

K. Kubo, X. Zheng, Y. Tanaka, H. Tamaki, T. Sugiyama, S. Jang, T. Takata, A. Yamaguchi, Simulation-based dynamic probabilistic risk assessment of an internal flooding-initiated accident in nuclear power plant using THALES2 and RAPID, Proceedings of the Institution of Mechanical Engineers, Part O: Journal of Risk and Reliability, 10.1177/1748006X221091604 (2022).

K. Kubo, S. Jang, T. Takata, A. Yamaguchi, Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants, Journal of Nuclear Science and Technology, Vol. 59, No. 3, pp. 357-367, 10.1080/00223131.2021.1971119 (2022).

T. Takata, M. Aoyagi, M. Sonehara, Numerical Assessment of Sodium Fire Incident, IAEA-TECDOC-1972, pp. 224-234, IAEA (2021).

小坂亘, 内堀昭寛, 柳沢秀樹, 高田孝, 工学近似を用いたナトリウム-水反応ジェット挙動評価用粒子法コードの研究, 日本機械学会論文集, Vol. 88, No. 905, 21-00310, 10.1299/transjsme.21-00310 (2021).

T. Sugimoto, A. Kaneko, Y. Abe, A. Uchibori, A. Kurihara, T. Takata, H. Ohshima, Droplet entrainment by high-speed gas jet into a liquid pool, Nuclear Engineering and Design, Vol. 380, 111306, 10.1016/j.nucengdes.2021.111306 (2021).

Y. Zhan, Y. Kuwata, T. Okawa, M. Aoyagi, T. Takata, Experimental study on secondary droplets produced during liquid jet impingement onto a horizon solid surface, Experimental Thermal and Fluid Science, Vol. 120, 110249, 10.1016/j.expthermflusci.2020.110249 (2021).