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Ohshima, Hiroyuki; Asayama, Tai; Furukawa, Tomohiro; Tanaka, Masaaki; Uchibori, Akihiro; Takata, Takashi; Seki, Akiyuki; Enuma, Yasuhiro
Journal of Nuclear Engineering and Radiation Science, 9(2), p.025001_1 - 025001_12, 2023/04
This paper describes the outline and development plan for ARKADIA to transform advanced nuclear reactor design to meet expectations of a safe, economic, and sustainable carbon-free energy source. ARKADIA will realize Artificial Intelligence (AI)-aided integrated numerical analysis to offer the best possible solutions for the design and operation of a nuclear plant, including optimization of safety equipment. State-of-the-art numerical simulation technologies and a knowledge base that stores data and insights from past nuclear reactor development projects and R&D are integrated with AI. In the first phase of development, ARKADIA-Design and ARKADIA-Safety will be constructed individually, with the first target of sodium-cooled reactor. In a subsequent phase, everything will be integrated into a single entity applicable not only to advanced rectors with a variety of concepts, coolants, configurations, and output levels but also to existing light-water reactors.
Uchibori, Akihiro; Sogabe, Joji; Okano, Yasushi; Takata, Takashi*; Doda, Norihiro; Tanaka, Masaaki; Enuma, Yasuhiro; Wakai, Takashi; Asayama, Tai; Ohshima, Hiroyuki
Proceedings of Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors (Internet), 10 Pages, 2022/09
The ARKAIDA has been developed to realize automatic optimization of plant design from safety evaluation for the advanced reactors represented by a sodium-cooled fast reactor. ARKADIA-Design offers functions to support design optimization both in normal operating conditions and design basis events. The multi-level simulation approach by the coupled analysis such as neutronics, core deformation, core thermal hydraulics was developed as one of the main technologies of the ARKADIA-Design. On the other hand, ARKAIDA-Safety aims for safety evaluation considering severe accidents. As a key technology, the numerical methods for in- and ex-vessel coupled phenomena during severe accidents in sodium-cooled fast reactors were tested through a hypothetical severe accident event.
Takase, Kazuyuki; Tamai, Hidesada; Yoshida, Hiroyuki; Akimoto, Hajime
Proceedings of International Meeting on Updates in Best EstimateMethods in Nuclear Installations Safety Analysis (BE-2004) (CD-ROM), p.151 - 152, 2004/11
no abstracts in English
Onuki, Akira
Nihon Kikai Gakkai Doryoku Enerugi Shisutemu Bumon Nyusu Reta, (29), p.3 - 5, 2004/10
no abstracts in English
Uchibori, Akihiro; Takata, Takashi; Fukano, Yoshitaka; Yamano, Hidemasa
no journal, ,
The development of ARKADIA-Safety for safety evaluation and design optimization considering severe accident was started. This development includes improvement and applicability expansion of the in- and ex-vessel analysis code, SPECTRA. Furthermore, optimization of the containment vessel considering severe accident will be performed as an example application of ARKADIA-Safety.
Ohshima, Hiroyuki; Asayama, Tai; Furukawa, Tomohiro; Tanaka, Masaaki; Takata, Takashi; Enuma, Yasuhiro
no journal, ,
For the purpose of supporting the concept examination and narrowing down of various nuclear reactor systems conducted in the private sector in nuclear innovation, we have started the development of AI-aided advanced reactor life cycle optimization method, ARKADIA, that integrates knowledge base and simulation technology to optimize design for innovative nuclear reactors including fast reactor and realize design and safety evaluation that make the most of past knowledge. This paper outlines the overall development plan.
Nakamura, Hirofumi
no journal, ,
This paper reports SMR's current status in the world and development status of advanced reactors in Japan.
Uchibori, Akihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Sogabe, Joji; Okano, Yasushi; Takata, Takashi*
no journal, ,
The ARKADIA-Safety for safety evaluation and design optimization considering severe accident has been developed. This paper presents validation of sodium fire analysis model and integration of ex-vessel analysis model for improvement of the evaluation method.
Koito, Yuko
no journal, ,
no abstracts in English
Okano, Yasushi; Uchibori, Akihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Ishida, Shinya; Sogabe, Joji; Takata, Takashi*
no journal, ,
no abstracts in English
Uchibori, Akihiro; Okano, Yasushi; Takata, Takashi*
no journal, ,
The evaluation tool, ARKADIA-Safety, has been developed to optimize a design considering safety and economy for advanced reactors such as sodium-cooled fast reactors. In this study, safety assessment for containment vessel during a sodium leak accident was performed to construct a design optimization process. The applied numerical method and evaluation process successfully provided some design conditions which meet the safety criteria and be excellent at economy.
