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Onoda, Yuichi; Chikazawa, Yoshitaka; Nakamura, Hironori*; Barbier, D.*; Dirat, J.-F.*
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
no abstracts in English
Suzuki, Toru; Sogabe, Joji; Tobita, Yoshiharu; Sakai, Takaaki*; Nakai, Ryodai
Nihon Kikai Gakkai Rombunshu (Internet), 83(848), p.16-00395_1 - 16-00395_9, 2017/04
no abstracts in English
Takeda, Takeshi; Tachibana, Yukio; Iyoku, Tatsuo; Takenaka, Satsuki*
Annals of Nuclear Energy, 30(7), p.811 - 830, 2003/05
Times Cited Count：1 Percentile：10.46(Nuclear Science & Technology)no abstracts in English
Takada, Eiji*; Fujimoto, Nozomu; Matsuda, Atsuko*; Nakagawa, Shigeaki
JAERI-Tech 2003-040, 23 Pages, 2003/03
JAERI-Tech-2003-040.pdf:1.28MB
In the High Temperature Engineering Test Reactor (HTTR), since the primary circuit is very high at the high temperature test operation, the special alloy Alloy800H is used as the metallic material for cladding tubes and spines of the control rods to endure the temperature of 950 degrees centigrade. The control rod is supposed to be exchanged for the excess use of its temperature limit 900 degrees centigrade according to the strength data of Alloy800H. The scram shutdown by loss of off-site electric power at the high temperature test operation is assumed as an event of the temperature of the control rods to exceed 900 degrees centigrade. In this report, the temperature of the control rods is analyzed by using the measurement data of the rise-to-power test. The result of this analysis it is confirmed that the control rod temperature does not exceed its limitation value even after the most temperature raises event of the loss of off-site electric power at the high temperature test operation.
Takeda, Takeshi; Tachibana, Yukio; Nakagawa, Shigeaki
JAERI-Tech 2002-091, 45 Pages, 2002/12
JAERI-Tech-2002-091.pdf:1.77MB
no abstracts in English
Takeda, Takeshi; Nakagawa, Shigeaki; Homma, Fumitaka*; Takada, Eiji*; Fujimoto, Nozomu
Journal of Nuclear Science and Technology, 39(9), p.986 - 995, 2002/09
Times Cited Count：5 Percentile：28.12(Nuclear Science & Technology)no abstracts in English
Takeda, Takeshi; Nakagawa, Shigeaki; Fujimoto, Nozomu; Tachibana, Yukio; Iyoku, Tatsuo
JAERI-Data/Code 2002-015, 39 Pages, 2002/07
JAERI-Data-Code-2002-015.pdf:1.53MB
no abstracts in English
Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Fujimoto, Nozomu; Shindo, Ryuichi; Sudo, Yukio
JAERI-M 91-165, 71 Pages, 1991/10
no abstracts in English
Zheng, X.; Shibamoto, Yasuteru
no journal, ,
Probabilistic Risk Assessment (PRA) modeling often requires extensive manual effort, specialized expertise, and the use of proprietary software, which can impose significant cost and accessibility barriers. This study investigates the feasibility of automating PRA model development by leveraging generative AI and open-source digital toolkits. A prototype workflow was developed that integrates the Google Gemini API with Python scripts, and employs the OpenPSA model exchange format alongside the SCRAM tool for model representation and analysis. A test implementation using Google AI Studio demonstrated the successful generation of PRA structures, such as event trees, from natural language descriptions. These results indicate that combining large language models with open-source tools can streamline PRA modeling, reduce development time, and lower the entry threshold for new practitioners. This approach holds promise not only for improving modeling efficiency and reducing costs in industry applications, but also for supporting education and training of the next generation of risk analysts by making PRA more accessible and interactive.
