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Uchibori, Akihiro; Doda, Norihiro; Aoyagi, Mitsuhiro; Sonehara, Masateru; Sogabe, Joji; Okano, Yasushi; Takata, Takashi*; Tanaka, Masaaki; Enuma, Yasuhiro; Wakai, Takashi; et al.
Nuclear Engineering and Design, 413, p.112492_1 - 112492_10, 2023/11
Times Cited Count：1 Percentile：72.91(Nuclear Science & Technology)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. 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. Improvement of the ex-vessel model and development of the AI technology to find best design solution have been started.
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.
Saito, Hiroshi; Nozawa, Takashi; Takemiya, Hiroshi; Seki, Akiyuki; Matsubara, Takeshi; Saito, Kimiaki; Kitamura, Akihiro
JAEA-Review 2017-040, 34 Pages, 2018/03
JAEA-Review-2017-040.pdf:9.52MB
The accidents at Fukushima Daiichi Nuclear Power Station on March 11th 2011, released significant amount of radionuclide to the environment. It has migrated to the human habitation and raised concerns of possible effect on human health, and for that a lot of researches have been performed. JAEA created and opened "Database for Radioactive Substance Monitoring Data" for usage of obtained data. For accurate modelling and future forecast using numerical code and the data, "Supporting Environment for Processing Simulation Codes" has been operated. In addition, research results have been opened as Q&A style "Knowledge Base for Environmental Remediation" in JAEA's website. The "Comprehensive Evaluation System" composed of these components, should act more interrelated and integrated as one system. Besides, information dissemination is not enough to the outside. The report summarizes the current status, remaining issues and expected improvement of each component and the system.
Kaji, Yoshiyuki; Yoshida, Kenji*; Mashiko, Shinichi*; Fujita, Mitsutane*; Shimura, Kazuki*; Kinugawa, Junichi*; Tsuji, Hirokazu; Miyakawa, Shunichi*; Iwata, Shuichi*
Dai-38-Kai Joho Kagaku Gijutsu Kenkyu Shukai Happyo Yokoushu, p.43 - 47, 2001/00
A distributed database system named Data-Free-Way for advanced nuclear materials has been developed by the National Institute for Materials Science (NIMS), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Cycle Development Institute (JNC), and the Japan Science and Technology Corporation (JST) under a cooperative agreement. In this system, end-users are able to obtain necessary data such as tables or graphs, even if they do not know the sites in which the data are stored. A distributed knowledge database in which each organization makes the knowledge based on the retrieval results from fact database and end-users can get the knowledge, has been developed to make more useful utilization of this system. Though the retrieval results from the fact database were shown in the tables or graphs, the new system constitutes the information notes described the retrieval ones for the knowledge by XML. This paper describes the present status of the Data-Free-Way and the description method of XML for the retrieval results.
Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu
"Fukanteki Kanten Karano Kogaku" Shimpojiumu Shiryoshu, p.175 - 178, 2000/11
no abstracts in English
Suzuki, Kazuhiko*; *
JNC TJ8400 2000-052, 136 Pages, 2000/02
JNC-TJ8400-2000-052.pdf:4.16MB
Though HAZOP is recognized as the useful safety assessment method, it requires a labor-intensive and time-consuming process. So recently computer-aided HAZOP has been proposed. The research report in 1999 (PNC TJ1400 99-003) presented HAZOP system based on the plant component malfunctions basic models. By using this basic model, not only state malfunction of component but also the consequence to external circumstance can be assessed. G2, which is an excellent object-oriented developer tool in GUI (Graphical User Interface), was used as a tool for developing the system. By using the graphical editor in the system, the user can carry out HAZOP easily. The purpose of this research is to improve the ability of the HAZOP system to obtain a more detailed HAZOP results. HAZOP is carried out according to the fault propagation of component level and the one of plant level based on plant component malfunctions basic models. Furthermore, the HAZOP system which can do the cause and effect analysis in detail intended for the component which processes two or more materials is developed. It is possible to carry out HAZOP for various plants by newly adding material information to the knowledgebase. We have applied this system to the Nuclear Reprocessing Facilities to demonstrate the utilities of developing system.
Kaji, Yoshiyuki; Sakino, Takao*; Ugachi, Hirokazu; Tsuji, Hirokazu
Proceedings of 9th German-Japanese Workshop on Chemical Information, p.121 - 124, 2000/00
no abstracts in English
Kinugawa, Junichi*; Fujita, Mitsutane*; Noda, Tetsuji*; Tsuji, Hirokazu; Kaji, Yoshiyuki; Sakino, Takao*; Tachi, Yoshiaki*; Kaneda, Kenichiro*; Mashiko, Shinichi*; Shimura, Kazuki*; et al.
Proceedings of 9th German-Japanese Workshop on Chemical Information, p.134 - 135, 2000/00
no abstracts in English
Fusaeda, Shigeki*; Yanagisawa, Ichiro*; Kataoka, Shinichi*; Shimada, Takashi*; *; *; *
PNC TJ1216 98-006, 673 Pages, 1998/02
None
*
PNC TJ9604 98-001, 83 Pages, 1997/03
Recently, due to the tremendous improvement of information infrastructures such as networking facilities, the idea of a large scale knowledge base with realtime operations for technological plants has emerged. The major bottleneck for building a large scale knowledge base for an autonomous plant lies in its design phase. The acquisition of knowledge from human experts in an exhaustive way is extremely difficult, and even if it were possible, the maintenance of such a large knowledge base for realtime operation is not an easy task. The autonomous system having just incomplete knowledge would face with so many problems that contradicts with the system's current beliefs and/or are novel or unknown to the system. Experienced humans can manage to do with such novelty due to their generalizing ability and analogical inference based on the repertoire of precedents, even if they with new problems. Moreover, through experiencing such breakdowns and impasse, they can acquire some novel knowledge by their proactive attempts to interpret a provided problem as well as by updating their beliefs and contents and organization of their prior knowledge. We call such a style of learning as impasse-driven learning, meaning that learning dose occur being motivated by facing with contradiction and impasse. The related studies concerning with such a style of learning have been studied within a field of machine learning of artificial intelligence so far as well as within a cognitive science field. In this paper, we at first summarize an outline of machine learning methodologies, and then, we detail about the impasse-driven learning. We discuss that from two different perspectives of learning, one is from deductive and analogical learning and the other one is from inductive conceptual learning (i.e., concept formation or generalization-based memory). The former mainly discuss about how the learning system updates its prior beiiefs and knowledge so that it can explain away the ...
*; Fusaeda, Shigeki*; Kataoka, Shinichi*; Nemoto, Kazuhiko*; Yanagisawa, Ichiro*; Fukui, Hiroshi*; Doi, Motoo*
PNC TJ1216 97-007, 77 Pages, 1997/03
None
; ; Yoshikawa, Shinji; Ozawa, Kenji
PNC TN9410 96-101, 40 Pages, 1996/04
Since it is desired to enhance availability and safety of nuclear power plants operation and maintenance by removing human factor, there are many researches and developments for intelligent operation or diagnosis using artificial intelligennce (AI) technique. We have been developing an autonomous operation and maintenance system for nuclear power plants by substituting AI's and intelligent robots. It is indispensable to use various and large scale knowledge relative to plant design, operation, and maintenance, that is, whole life cycle data of the plant for the autonomous nuclear power plant. These knowledge must be given to AI system or intelligent robots adequately and opportunely. Moreover, it is necessaly to insure real time operation using the large scale knowledge base for plant control and diagnosis performance. We have been studying on the large scale and real time knowledge base system for autonomous plant. In the report, we would like to present the basic concept and expecting performance of the knowledge base for autonomous plant, especialy, autonomous control and diagnosis system.
; Yokobayashi, Masao; Tanabe, Fumiya; *
Journal of Nuclear Science and Technology, 33(2), p.110 - 118, 1996/02
Times Cited Count：2 Percentile：24.74(Nuclear Science & Technology)no abstracts in English
; Yokobayashi, Masao; *; Tanabe, Fumiya
Symbiosis of Human and Artifact: Future Computing and Design for Human-Computer Interaction,20A, 0, p.939 - 944, 1995/00
no abstracts in English
Yokobayashi, Masao; Matsumoto, Kiyoshi; Murayama, Yoji; Kaminaga, Masanori; Kosaka, Atsuo
JAERI-M 90-207, 26 Pages, 1990/11
no abstracts in English
; Yokobayashi, Masao
JAERI-M 89-184, 157 Pages, 1989/11
no abstracts in English
