Proceedings
of international peer-reviewed conferences
2024
H. Tanaka, T. Narukawa, T. Takata, Probabilistic Approach for Best Estimate of Fuel Rod Fracture, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1184, Sendai, Japan, October, 2024.
S. Hamaguchi, T. Narukawa, T. Takata, A Bayesian Approach for Designing Experiments Based on Information Criteria to Reduce Prediction Uncertainty of Fuel Fracture during LOCA, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1073, Sendai, Japan, October, 2024.
P. Janta, K. Silva, T. Takata, T. Narukawa, N. Chollacoop, Development of Conceptual Framework for Adaptive State for Energy Resilience Assessment of Clean Energy Systems, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1321, Sendai, Japan, October, 2024.
N. Yamamoto, M. Kagimoto, Y. Ueno, T. Narukawa, T. Takata, Application of Dynamic PRA to Nuclear Power Plant Operation Support - Evaluation of Plant Operation Support Using a Simple Plant Model, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1123, Sendai, Japan, October, 2024.
X. Zheng, H. Tamaki, Y. Shibamoto, Y. Maruyama, T. Takada, T. Narukawa, T. Takata, Development of Risk Importance Measures for Dynamic PRA Based on Risk Triplet (2) Trial Measurement of Risk Importance Through Dynamic Level 2 PRA With RAPID, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1138, Sendai, Japan, October, 2024.
T. Narukawa, T. Takata, X. Zheng, H. Tamaki, Y. Shibamoto, Y. Maruyama, T. Takada, Development of Risk Importance Measures for Dynamic PRA Based on Risk Triplet (1) The Concept and Measures of Risk Importance, Proceedings of Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024), PSAM17&ASRAM2024-1026, Sendai, Japan, October, 2024.
T. Narukawa, Y. Udagawa, Uncertainty Analysis of Model Selection Based on Information Criterion: A Case Study of a Probability Estimation Model for Fuel Cladding Tube Fracture during LOCA , Proceedings of 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27), 10 Pages, Yokohama, Japan, March, 2024.
2023
T. Narukawa, S. Hamaguchi, T. Takata, Epistemic Uncertainty Reduction in Fuel Fracture Limit During LOCA Through Bayesian Updating Based on Information Criterion, Proceedings of Asian Symposium on Risk Assessment and Management 2023 (ASRAM 2023), 3 Pages (Extended Abstract), Hong Kong, China, December, 2023.
P. Janta, K. Thapmanee, K. Vithean, N. Chollacoop, W. Vechgama, T. Takata, T. Narukawa, K. Silva, Differences in Assumptions, Inputs, and Outputs between Energy Resilience Assessments for Renewable Energy and Nuclear Power Systems, Proceedings of Asian Symposium on Risk Assessment and Management 2023 (ASRAM 2023), 8 Pages, Hong Kong, China, December, 2023.
2022
T. Narukawa, S. Hamaguchi, T. Takata, Y. Udagawa, Hierarchical Bayes Model to Quantify Fracture Limit Uncertainty of High-burnup Advanced Fuel Cladding Tubes under LOCA Conditions, Proceedings of Asian Symposium on Risk Assessment and Management (ASRAM2022), 11 Pages, Daejeon, Korea, November, 2022.
M. Aoyagi, A. Uchibori, T. Takata, Development of the sodium pool and floor concrete module for the integrated SFR safety analysis code, SPECTRA, Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 13 Pages, March, 2022.
W. Kosaka, A. Uchibori, T. Takata, H. Yanagisawa, A. Watanabe, S. Jang, Development of reacting jet evaluation model based on engineering approaches with particle method for improvement of LEAP-III code, Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 11 Pages, March, 2022.
2021
N. Hirokawa, A. Yamaguchi, T. Takata, S. Jang, Qualitative Risk Analysis on Primary Containment Vessel Venting using STAMP/STPA, Proceedings of Asian Symposium on Risk Assessment and Management (ASARAM 2021), Online, October, 2021.
W. Kosaka, A. Uchibori, H. Yanagisawa, T. Takata, S. Jang, Numerical evaluation of sodium-water reaction based on engineering approach with particle method, Proceedings of 28th International Conference on Nuclear Engineering; Nuclear Energy the Future Zero Carbon Power (ICONE 28) (Internet), 6 Pages, Aaugust, 2021.
M. Aoyagi, D. L. Y. Louie, A. Uchibori, T. Takata, D. Luxat, Study of recent sodium pool fire model improvements for MELCOR code, Proceedings of 28th International Conference on Nuclear Engineering; Nuclear Energy the Future Zero Carbon Power (ICONE 28) (Internet), 6 Pages, Aaugust, 2021.
2020
K. Kubo, X. Zheng, J. Ishikawa, T. Sugiyama, S. Jang, T. Takata, A. Yamaguchi, Case study on sampling techniques using machine learning and simplified physical model for simulation-based dynamic probabilistic risk assessment, Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020), Online, November, 2020.
K. Kubo, X. Zheng, Y. Tanaka, H. Tamaki, T. Sugiyama, S. Jang, T. Takata, A. Yamaguchi, Dynamic PRA of flooding-initiated accident scenarios using THALES2-RAPID, Proceedings of the 30th European Safety and Reliability Conference and the 15th Probabilistic Safety Assessment and Management Conference (ESREL2020-PSAM15), Online, November, 2020.
K. Kubo, X. Zheng, Y. Tanaka, H. Tamaki, T. Sugiyama, S. Jang, T. Takata, A. Yamaguchi, A comparative study of sampling techniques for dynamic probabilistic risk assessment of nuclear power plants, Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA+MC2020), Makuhari, Japan, May, 2020.