Articles

in peer-reviewed journals

2024

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, 10.1080/00223131.2024.2321342 (2024).

2023

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, 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).
N. Hirokawa, A. Yamaguchi, T. Takata, T. Narukawa, Method of Analyzing Criteria for Primary Containment Vessel Venting and Protective Measures for Public Risk Reduction, Transactions of the Atomic Energy Society of Japan, Vol. 22, No. 1, p. 25-37, 10.3327/taesj.J22.003 (2023).

2022

N. Hirokawa, A. Yamaguchi, T. Takata, S. Jang, Qualitative Risk Analysis on Primary Containment Vessel Venting using STAMP/STPA, Transactions of the Atomic Energy Society of Japan, 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).

2021

T. Takata, M. Aoyagi, M. Sonehara, Numerical Assessment of Sodium Fire Incident, IAEA-TECDOC-1972, pp. 224-234, IAEA (2021).
W. Kosaka, A. Uchibori, H. Yanagisawa, T. Takata, Study on sodium-water reaction jet evaluation model based on engineering approaches with particle method, Transactions of the JSME (in Japanese), 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).