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Uchibori, Akihiro; Okano, Yasushi
Isotope News, (793), p.32 - 35, 2024/06
The design of a containment vessel in a sodium-cooled fast reactor was optimized from simulation on the hypothetical severe accident including sodium leakage and combustion. The simulation method is one of the base technologies of the design optimization system, ARKADIA. The simulation was performed on the different design conditions including volume of the containment vessel and the safety equipment as optimization parameters. The iterative simulation successfully found that the safety under this accident was kept even in the downsized containment vessel by selecting an effective safety equipment. This study demonstrated that the developed method has basic capability for design optimization in ARKADIA.
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.
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.
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.
Kamide, Hideki; Shibata, Taiju
NREL/TP-6A50-77088 (Internet), p.35 - 38, 2020/09
Hayafune, Hiroki; Maeda, Seiichiro; Ohshima, Hiroyuki
Nihon Genshiryoku Gakkai-Shi ATOMO
, 61(11), p.798 - 803, 2019/11
In the "Strategic Roadmap" of Fast Reactor Development decided at the Inter-Ministerial Council for Nuclear Power in December 2018, the development works for the around next 10 years were identified, and the role of JAEA was presented. In response, JAEA has prepared a framework for R&D plans for about 5 years on the fast reactor technology and the fuel cycle technology (reprocessing, fuel manufacturing, fuel and material development). In the future, JAEA will promote independent R&D works based on these plans, and provide the obtained R&D results together with various testing functions of JAEA to the activities of the private sector, etc. Through these actions, JAEA will actively contribute to the future fast reactor development. This article outlines JAEA's policy and the R&D items (development of ARKADIA; Advanced Reactor Knowledge- and AI-Aided Design Integration Approach through the whole Plant Life Cycle, development of standards and standards system, development of safety improvement technology, research in the fuel cycle technology), the policy of international cooperation, the human resource development, and the future perspective were explained.
Tanaka, Masaaki
no journal, ,
Japan Atomic Energy Agency (JAEA) is promoting research and development (R&D) related to fast reactors and nuclear fuel cycles as a contribution to carbon neutrality through the investigation of innovative technologies such as safety improvement. In order to maintain, develop, and provide the technological infrastructure for nuclear power plant innovation, that is the role of JAEA, an integrated evaluation method "ARKADIA" is under development to create innovative plant concepts and reform of the development process utilizing the wide range of knowledge cultivated through the development of fast reactors in JAEA. This presentation introduces the current status of development of sodium-cooled fast reactors and the ARKADIA-Design as a part of ARKADIA for design optimization support to address the R&Ds on thermal-hydraulics-related issues for design evaluation.
Tanaka, Masaaki
no journal, ,
The numerical analysis and evaluation technology base, including thermal hydraulic CFD technology is being developed in the integrated evaluation system named "ARKADIA" at the Japan Atomic Energy Agency. Regarding the deployment of thermal hydraulic CFD technology for the development of sodium-cooled fast reactors (SFR), application strategy of the technology base in ARKADIA to the conceptual design process of the demonstration SFR was briefly introduced, touching on the experiences of the application study to the new regulatory standards for "Joyo". The development of knowledge (KMS) - simulation (VLS) linkage function to concrete capitalization and effectively utilization of the experiences (knowledge) of the numerical analyses in JAEA was also introduced. And furthermore, the extension of the whole plant analysis method being developed in ARKADIA to the digital twin technology in the SFR development was mentioned.
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.
Tanaka, Masaaki; Ezure, Toshiki; Yoshikawa, Ryuji; Doda, Norihiro; Mori, Takero; Hamase, Erina; Yoshimura, Kazuo; Kikuchi, Norihiro; Matsushita, Kentaro; Mochinaga, Shota
no journal, ,
This brief presents the outline of the evaluation support program on the evaluations of the thermal-hydraulics related issues in the conceptual design study of the sodium-cooled fast reactor for demonstration in Japan over the five years, utilizing the technical basis on the simulations and evaluations configured in the integrated evaluation system named ARKADIA that has been developed with experiences through the development of the SFRs and related R&Ds in Japan Atomic Energy Agency.
Yamano, Hidemasa
no journal, ,
This reports R&D for sodium-cooled fast reactors in Japan.
Kondo, Yuki; Hashidate, Ryuta; Hamase, Erina; Ezure, Toshiki; Mitsumoto, Rika; Yada, Hiroki; Enuma, Yasuhiro
no journal, ,
JAEA has started the development of Advanced Reactor Knowledge-and AI-aided Design Integration Approach through the whole plant lifecycle (ARKADIA) that performs integrated design evaluation and optimization from various viewpoints such as safety, economy, and maintainability using risk information, in order to dramatically improve the development efficiency of innovative reactors. In this paper, we report the concept of a knowledge management system to support integrated design evaluation and optimization, and the realization of the knowledge base necessary for the design and optimization of innovative reactors.
