Numerical simulation technologies for safety evaluation in plant lifecycle optimization method, ARKADIA for advanced reactors

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

https://doi.org/10.1016/j.nucengdes.2023.112492

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.

ARKADIA; For the innovation of advanced nuclear reactor design

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

https://doi.org/10.1115/1.4054726

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.

Data analysis based upon abduction; For better understanding the result discussion in computational science and engineering

Nakajima, Norihiro

Nihon Genshiryoku Gakkai-Shi ATOMO, 59(8), p.34 - 38, 2017/08

It is necessary the reading comprehension of output data to utilize the simulation in a design process, besides of the input data preparation. The simulation introduces enormous big data for evaluation. This paper describes data analysis technology in the analysis and the evaluation process of the output. The technology applies the artificial intelligence to minimize the unpredictable issues and oversight. It is based on the artifact engineering, which is a multi-sight abduction methodology, which derives a hypothesis.

JACOS AI-based simulation system for man-machine system behavior in NPP

Yoshida, Kazuo; Yokobayashi, Masao; Tanabe, Fumiya; Kawase, Katsumi*; Komiya, Akitoshi*

JAERI-Data/Code 2001-023, 118 Pages, 2001/08

JAERI-Data-Code-2001-023.pdf:8.65MB

no abstracts in English

Radiation control monitor and data processing on HTTR

Nomura, Toshibumi

Hoken Butsuri, 35(1), p.127 - 135, 2000/03

https://doi.org/10.5453/jhps.35.127

no abstracts in English

Devdopment of an intellectual maintenance management system; Development of trouble detection and troubleshooting evaluation system

; Tani, Satoshi; Yoshikawa, Shinji

PNC TN9410 98-023, 29 Pages, 1998/03

PNC-TN9410-98-023.pdf:1.33MB

Many research activities are conducted to enhance cost performance and safety of nuclear power plants operation and maintenance. Concept of autonomous operating system to equal the role of operators and of maintenance personnel with artificial intelligence and autonomous robots has been developed. An intellectual maintenance management system has been developed to be equipped with decision making functions of maintenance personnel. The intellectual maintenance management system is in charge of maintenance function of an autonomous plant, which consists of plant-wide monitoring, evaluation of component integrity, and scheduling of maintenance activities. In other words, this system should be equipped with preventive maintenance and corrective maintenance functions those are currently loaded on personnel. In this report, we discussed condition monitoring maintenance in the preventive maintenance. We also reported a sensor validation system development for machinery condition monitoring and diagnosis. We adopted distributed and cooperative system construction technique, which is expected recently in applications to large-scale plants. This system has inter-agent communication function for signal transmission and reception among distributed physics models of machineries. The system has been constructed for water / steam system of the LMFBR power plant. The system has been validated to be capable of cooperative sensor validation by the distributed set of agents, with quantitative indication of sensor deviation based on a newly developed fuzzy algorithm with inter-agent cooperation. The derived reference parameter value from the inter-agent evaluations also stands for the alternative measurment to the malfunctioned sensor.

Surveys of System Safety Assessment Methods (II)

Sayama, Hayatoshi*; Suzuki, Kazuhiko*; Shimada, Yukiyasu*

PNC TJ1612 96-001, 84 Pages, 1996/03

PNC-TJ1612-96-001.pdf:2.5MB

no abstracts in English

Artifical intelligence may be growing up in the large complex system of machine

Shimooke, Takanori

Kikai Sekkei, 33(8), p.117 - 122, 1989/08

no abstracts in English

Applications of an AI method to optimum reactor control problems

Shinohara, Yoshikuni

Artifical Intelligence and Other Innovative Computer Applications in the Nuclear Industry, 8 Pages, 1987/00

no abstracts in English

Feasibility study for enhancing probabilistic risk assessment methodology by using AI technology, 1; Development plan of AI tools

Futagami, Satoshi; Yamano, Hidemasa; Kurisaka, Kenichi; Ujita, Hiroshi*

no journal, , 

To create an innovation for efficient and effective social implementation of nuclear power plant PRA, automatic construction tool for fault tree architecture and automatic failure judgment tool to construct reliability database are developed by using AI and digitization technology. In this meeting, development plan of AI tools is reported.