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Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Doda, Norihiro; Tanaka, Masaaki
Annals of Nuclear Energy, 225, p.111754_1 - 111754_10, 2025/01
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)Doda, Norihiro; Nakamine, Yoshiaki*; Yoshimura, Kazuo; Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Kikuchi, Norihiro; Mori, Takero; Hashidate, Ryuta; Tanaka, Masaaki
Keisan Kogaku Koenkai Rombunshu (CD-ROM), 29, 6 Pages, 2024/06
As a part of the development of the "Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle (ARKADIA)" to utilize the knowledge obtained through the sodium-cooled fast reactors (SFRs) and combine the latest numerical simulation technologies, ARKADIA-Design is being developed to support the optimization of SFRs in the conceptual design stage. ARKADIA-Design consists of three systems of Virtual Plant Life System (VLS), Enhanced and AI-aided optimization System (EAS), and Knowledge Management System (KMS). A design optimization framework controls the linkage among the three systems through the interfaces in each system. In this study, we have developed a prototype of the framework for core design optimization using the coupled analysis functions in VLS and optimization control function in the linkage of EAS and VLS to investigate the applicability of the framework to the SFR design optimization process.
Hamase, Erina; Kuwagaki, Kazuki; Doda, Norihiro; Yokoyama, Kenji; Tanaka, Masaaki
Mechanical Engineering Journal (Internet), 11(2), p.23-00440_1 - 23-00440_14, 2024/04
The core design optimization process is being developed as part of the design optimization support tool named ARKADIA-Design. The process performs the integrated analysis with neutronics, thermal-hydraulics, fuel integrity, and plant dynamics using the Bayesian optimization (BO) algorithm, and obtains the optimal design parameters efficiently. In this study, the representative problem was defined based on core design experiences, and the process was specified. To confirm the appropriateness of the definition of representative problem, as a minimum requirement, the single-objective optimization problem was solved by the integrated analysis with neutronics and plant dynamics using the BO. We found the existence of the optimal solution and the agreement between this solution and the reference one. There was the prospect that the process was applicable to the representative problem.
Doda, Norihiro; Kato, Shinya; Hamase, Erina; Kuwagaki, Kazuki; Kikuchi, Norihiro; Ohgama, Kazuya; Yoshimura, Kazuo; Yoshikawa, Ryuji; Yokoyama, Kenji; Uwaba, Tomoyuki; et al.
Proceedings of 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (Internet), p.946 - 959, 2023/08
An innovative design system named ARKADIA is being developed to realize the design of advanced nuclear reactors as safe, economical, and sustainable carbon-free energy sources. This paper focuses on ARKADIA-Design for design studies as a part of ARKADIA and introduces representative verification methods for numerical analysis methods of the core design. ARKADIA-Design performs core performance analysis of sodium-cooled fast reactors using a multiphysics approach that combines neutronics, thermal-hydraulics, core mechanics, and fuel pin behavior analysis codes. To confirm the validity of these analysis codes, validation matrices are identified with reference to experimental data and reliable numerical analysis results. The analysis models in these codes and the representative practices for the validation matrices are described.
Hamase, Erina; Kuwagaki, Kazuki; Doda, Norihiro; Yokoyama, Kenji; Tanaka, Masaaki
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 10 Pages, 2023/05
To innovate a core design process, an optimization process for the core design has been developed as a part of the design optimization support tool named ARKADIA-Design. The core design optimization process is integrated by the core design analysis of neutronics, thermal-hydraulics, and fuel integrity and plant dynamics analysis with the Bayesian optimization (BO) algorithm. The optimization problem for design parameters with high core performance and inherent safety in ULOF event was solved by the integrated analysis between the neutronics and plant dynamics with the BO in a primary loop system including a core consisting of two-dimensional RZ cylindrical geometry. It was indicated that the optimization process could obtain an optimal solution.
Doda, Norihiro; Yoshimura, Kazuo; Hamase, Erina; Yokoyama, Kenji; Uwaba, Tomoyuki; Tanaka, Masaaki
Proceedings of Technical Meeting on State-of-the-art Thermal Hydraulics of Fast Reactors (Internet), 3 Pages, 2022/09
ARKADIA-Design is being developed to support the optimization of sodium-cooled fast reactors in the conceptual design stage. Design optimization requires various types of numerical analysis: 1-D plant dynamics analysis for efficient evaluation of various design options and multi-dimensional analysis for a detailed evaluation of local phenomena, including multi-physics. For those analyses, ARKADIA-Design performs whole plant analyses based on the multi-level simulation (MLS) technique in which the analysis codes are coupled to simulate the phenomena in an intended degree of resolution. This paper describes an outline of the coupling analysis methods in the MLS of the ARKADIA-Design and the numerical simulations of the experimental fast breeder reactor EBR-II tests by the coupled analysis.
Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
Doda, Norihiro; Hamase, Erina; Yokoyama, Kenji; Tanaka, Masaaki
Keisan Kogaku Koenkai Rombunshu (CD-ROM), 25, 4 Pages, 2020/06
With the aim of advancing the design optimization in fast reactors, neutronics and thermal-hydraulics coupled analysis method which can consider the temporal change of neutron flux distribution in the core has been developed. A three-dimensional neutronics analysis code and a plant dynamics analysis code are coupled on a platform using Python programing. In this report, outlines of the coupling method of analysis codes, the results of its application to the actual plant under a virtual accidental condition, and the future development is described.
Yamagishi, Akihiko*; Yokobori, Shinichi*; Hashimoto, Hirofumi*; Yano, Hajime*; Imai, Eiichi*; Okudaira, Kyoko*; Kawai, Hideyuki*; Kobayashi, Kensei*; Tabata, Makoto*; Nakagawa, Kazumichi*; et al.
no journal, ,
no abstracts in English
Hamase, Erina; Kuwagaki, Kazuki; Doda, Norihiro; Yokoyama, Kenji; Tanaka, Masaaki
no journal, ,
A core design optimization process is developed as part of the design optimization support tool named ARKADIA-Design for an efficient and innovative core design process. The process comprises analyses integrated by neutronics, thermal-hydraulics in a fuel assembly, fuel integrity, and plant dynamics for safety assessment. The core design optimization problem in the sodium-cooled fast reactor that achieves to the prevention of the core damage during ULOF and the high core performance was set as a representative problem. The automatic optimization with integrated analysis between neutronics and plant dynamics by using the PSSP of ARKADIA-Design was realized. The prospect of applying this process to the core design was confirmed.
Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
no abstracts in English
Hamase, Erina; Kuwagaki, Kazuki; Doda, Norihiro; Yokoyama, Kenji; Tanaka, Masaaki
no journal, ,
To improve efficiency and innovate the core design process by decreasing the excessive conservativeness using a function of the design optimization support tool named ARKADIA-Design, firstly, the optimization process that provides the core design specifications with high core performance and inherent safety in ULOF event has been developed. The objective function in the optimization problem is set with the indexes of core performance and thermal transient loads for the simplified loop model. The problem is solved by the coupled analysis between the core design analysis and plant dynamics analysis with Bayesian optimization (BO). It was indicated that the optimization process using the neutronics and plant dynamics analysis with BO in a single objective function could obtain the optimal solution.
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.
Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
no abstracts in English
Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
no abstracts in English
Kuwagaki, Kazuki; Hamase, Erina; Yokoyama, Kenji; Doda, Norihiro; Tanaka, Masaaki
no journal, ,
no abstracts in English
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.
Hamase, Erina; Kuwagaki, Kazuki; Doda, Norihiro; Yokoyama, Kenji; Tanaka, Masaaki
no journal, ,
As part of innovative evaluation system named ARKADIA, a core design support process using Bayesian optimization has been developed by integrating core design analyses and safety analyses. A simplified fast reactor plant model was used as a representative case to evaluate core designs that maintain high core performance while avoiding core damage during ULOF events. The process successfully derived core specifications that minimize initial Pu fissile inventory while satisfying all design constraints, confirming its applicability to core design.
