Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Doda, Norihiro; Nakamine, Yoshiaki*; Kuwagaki, Kazuki; Hamase, Erina; Kikuchi, Norihiro; Yoshimura, Kazuo; Matsushita, Kentaro; Tanaka, Masaaki
Keisan Kogaku Koenkai Rombunshu (CD-ROM), 28, 5 Pages, 2023/05
As a part of the development of the "Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle (ARKADIA)" to automatically optimize the life cycle of innovative nuclear reactors including fast reactors, ARKADIA-design is being developed to support the optimization of fast reactor in the conceptual design stage. ARKADIA-Design consists of three systems (Virtual plant Life System (VLS), Evaluation assistance and Application System (EAS), and Knowledge Management System (KMS)). A design optimization framework controls the connection between the three systems through the interfaces in each system. This paper reports on the development of an optimization analysis control function that performs design optimization analysis combining plant behavior analysis by VLS and optimization study by EAS.
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.
Tanaka, Masaaki; Doda, Norihiro; Yokoyama, Kenji; Mori, Takero; Okajima, Satoshi; Hashidate, Ryuta; Yada, Hiroki; Oki, Shigeo; Miyazaki, Masashi; Takaya, Shigeru
Dai-26-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 5 Pages, 2022/07
To assist conceptual studies of various reactor systems conducted by private sectors in nuclear power innovation, development of an innovative design system named ARKADIA (Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle) is undergoing to achieve the design of an advanced nuclear reactor as a safe, economic, and sustainable carbon-free energy source. In this paper, focusing on the ARKADIA-Design as a part of it, the progress in the development of optimization processes on the representative problems in the fields of the core design, the plant structure design, and the maintenance schedule planning are introduced.
Doda, Norihiro; Nakamine, Yoshiaki*; Igawa, Kenichi*; Iwasaki, Takashi*; Murakami, Satoshi*; Tanaka, Masaaki
Keisan Kogaku Koenkai Rombunshu (CD-ROM), 27, 6 Pages, 2022/06
As a part of the development of the "Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle (ARKADIA)" to automatically optimize the life cycle of innovative nuclear reactors including fast reactors, ARKADIA-design is being developed to support the optimization of fast reactor design in the conceptual stage. ARKADIA-Design consists of three systems (Virtual plant Life System (VLS), Evaluation assistance and Application System (EAS), and Knowledge Management System (KMS)). A design optimization framework controls the cooperation between the three systems through the interfaces in each system. This paper reports on the development status of the "VLS interface," which has a control function of coupling analysis codes in VLS.
Tanaka, Masaaki; Doda, Norihiro; Mori, Takero; Yokoyama, Kenji; Uwaba, Tomoyuki; Okajima, Satoshi; Matsushita, Kentaro; Hashidate, Ryuta; Yada, Hiroki
Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03
Japan Atomic Energy Agency is developing an innovative design system named ARKADIA to achieve the design of an advanced nuclear reactor as a safe, economic, and sustainable carbon-free energy source. In the first phase of its development, ARKADIA-Design for design study and ARKADIA-Safety for safety assessment will be developed individually. In this paper, focusing on the ARKADIA-Design, the concept of the system is described and numerical analysis codes to be used for the multi-level and multi-physics analyses are introduced. Descriptions of the practical functions composed by the analysis codes and the representative problems in application studies for validation are introduced.
Tanaka, Masaaki; Oki, Shigeo; Miyazaki, Masashi; Takaya, Shigeru; Yokoyama, Kenji; Ando, Masanori
no journal, ,
Design optimization support tool named ARKADIA-Design for diverse nuclear power plant has been developing in Japan Atomic Energy Agency. Its development plans, goals, and schedules in the fields of core, plant structure including thermal-hydraulics, and maintenance are presented with brief introduction of progress at present.
Enuma, Yasuhiro; Kondo, Yuki; Hashidate, Ryuta; Mitsumoto, Rika; Hazama, Taira
no journal, ,
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.
Kuwagaki, Kazuki; Yokoyama, Kenji
no journal, ,
no abstracts in English
Enuma, Yasuhiro; Kondo, Yuki; Hashidate, Ryuta; Mitsumoto, Rika; Hazama, Taira; Demachi, Kazuyuki*
no journal, ,
no abstracts in English
Tanaka, Masaaki; Doda, Norihiro; Yokoyama, Kenji; Mori, Takero; Okajima, Satoshi; Hashidate, Ryuta; Yada, Hiroki; Oki, Shigeo; Miyazaki, Masashi; Takaya, Shigeru
no journal, ,
Design optimization support tool named ARKADIA-Design for diverse nuclear power plant is being developed in Japan Atomic Energy Agency. To implement the design optimizations in the fields of core, plant structure, and maintenance, development of the numerical analysis methods including a coupled analysis to evaluate the plant performance and installation of the procedure in each optimization process are investigated.
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.
Okano, Yasushi; Uchibori, Akihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Ishida, Shinya; Sogabe, Joji; Takata, Takashi*
no journal, ,
no abstracts in English
Tanaka, Masaaki; Doda, Norihiro; Hamase, Erina; Yoshimura, Kazuo; Ezure, Toshiki; Seki, Akiyuki; Yokoyama, Kenji; Miyazaki, Masashi; Oki, Shigeo
no journal, ,
Design optimization support tool named ARKADIA-Design for diverse nuclear power plant is being developed in Japan Atomic Energy Agency. In the implementation of the numerical evaluation of the plant performance and the design optimization process in ARKADIA-Design, the outline and development status of linkage functions of collecting the necessary information from and storing the results as new knowledge to the databases in the Knowledge Management System are presented.
Enuma, Yasuhiro; Yoshikawa, Masanori; Kondo, Yuki; Hashidate, Ryuta; Seki, Akiyuki; Yokoyama, Kenji; Takaya, Shigeru; Mitsumoto, Rika; Hazama, Taira
no journal, ,
no abstracts in English
Matsushita, Kentaro; Ezure, Toshiki; Imai, Yasutomo*; Tanaka, Masaaki
no journal, ,
Japan Atomic Energy Agency (JAEA) is developing AI-aided advanced reactor life cycle optimization method, ARKADIA, in order to support the development of various reactor systems, including sodium-cooled fast reactors (SFRs). One of the important thermal-hydraulic issues in SFR design is the suppression of cover gas entrainment caused by dip vortices in the free surface of the upper plenum of the reactor, and JAEA is developing gas entrainment evaluation system centered on the gas entrainment evaluation tool, StreamViewer, in ARKADIA. In this report, the overview of gas entrainment evaluation system in ARKADIA and the development status of StreamViewer are reported. In addition, the results of applying StreamViewer to the analysis results of the water flow test system and confirming that it is possible to evaluate the gas entrainment phenomenon are reported.
Uchibori, Akihiro; Shiina, Yoshimi*; Imai, Yasutomo*; Okano, Yasushi
no journal, ,
The design of a containment vessel in a sodium-cooled fast reactor was optimized from numerical analysis on the hypothetical severe accident including sodium leakage and combustion. The analysis method is one of the base technologies of the design optimization system, ARKADIA. The numerical analysis was performed on the different design conditions including volume of the containment vessel and the safety equipment as optimization parameters. The iterative numerical analysis successfully found that the safety under this accident was kept even in the downsized containment vessel by selecting an effective safety equipment. This numerical analysis demonstrated the basic capability of design optimization in ARKADIA.
Tanaka, Masaaki; Doda, Norihiro; Hamase, Erina; Kuwagaki, Kazuki; Mori, Takero; Okajima, Satoshi; Kikuchi, Norihiro; Hashidate, Ryuta; Yada, Hiroki; Yokoyama, Kenji; et al.
no journal, ,
In Japan Atomic Energy Agency, a design optimization support tool named ARKADIA-Design is being developed for advanced nuclear power plant system including sodium-cooled fast reactor (SFR). Achievements in the development of optimization processes in the fields of the core design, the plant structure design, and the maintenance schedule planning, as major function of ARKADIA-Design, are summarized at this point in time and challenges for further development in the next step are discussed.
Enuma, Yasuhiro; Yoshikawa, Masanori; Kondo, Yuki; Hashidate, Ryuta; Seki, Akiyuki; Yokoyama, Kenji; Takaya, Shigeru; Hazama, Taira
no journal, ,
no abstracts in English
