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Kato, Atsushi; Yamamoto, Tomohiko; Ando, Masato; Chikazawa, Yoshitaka; Murakami, Hisatomo*; Oyama, Kazuhiro*; Kaneko, Fumiaki*; Higurashi, Koichi*; Chanteclair, F.*; Chenaud, M.-S.*; et al.
EPJ Nuclear Sciences & Technologies (Internet), 8, p.11_1 - 11_10, 2022/06
This paper provides an overview of plant system studies to establish a common technical view for Sodium-cooled Fast Reactor concept between France and Japan based on ASTRID600 and the new concept with downsized output called ASTRID150. One of important issues on a reactor structure design is to enhance seismic resistance to be tolerable against strong earthquake such that postulated in Japan. A concept of High Frequency Design is shared, and the design options related to HFD have been examined and design recommendations are established. In addition, this paper include results of studies for a steam generator, a decay heat removal system, a fuel handling system and a containment vessel.
Sagayama, Yutaka; Ando, Masato
Nihon Genshiryoku Gakkai-Shi ATOMO
, 60(3), p.162 - 167, 2018/03
The Generation IV international Forum (GIF) has led international collaborative efforts to develop six next generation nuclear energy systems, such as Sodium-cooled Fast Reactor (SFR), Lead-cooled Fast Reactor (LFR), Gas-cooled Fast Reactor (GFR), Molten Salt Reactor (MSR), Supercritical Water-cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR), which have superior characteristics for the Safety and Reliability, Economics, Sustainability, Proliferation Resistance and Physical Protection. Some systems are already in the Demonstration Phase and the commercialization of the system in 2030s, which is the target of GIF, comes into sight.
Kamide, Hideki; Ando, Masato*; Ito, Takaya*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
JAEA, JAPC and MFBR have been conducted design study for the Japan Sodium-cooled Fast Reactor (JSFR), which is a design concept aiming at future commercial use as sustainable electric power source. Since 2011, in order to contribute to the development of safety design criteria (SDC) and safety design guideline (SDG), which include the lesson learned from the TEPCO's Fukushima Dai-ichi Nuclear Power Plants accident, in the frame work of generation IV international forum (GIF), the design study is focusing on the design measures against sever external events such as earthquake and tsunami. At the same time, the design study is going into detail and paying much attention to the maintenance and repair to make surer its feasibility. This paper summarizes the design concept of the demonstration version of JSFR in which progress of design work was incorporated.
Chikazawa, Yoshitaka; Okano, Yasushi; Konomura, Mamoru; Sato, Koji; Sawa, Naoki*; Sumita, Hiroyuki*; Nakanishi, Shigeyuki*; Ando, Masato*
Nuclear Technology, 159(3), p.267 - 278, 2007/09
Times Cited Count：1 Percentile：11.32(Nuclear Science & Technology)A diversified or modular power source is attractive since it requires a low construction cost per unit and can be demonstrated in small scale experimental facilities. In this study, a new metal fuel sodium cooled reactor with 300MW electric has been developed enhancing cost reduction. And economical potential at demonstration stage with first of a kind (FOAK) is emphasized. A minimum configuration with a compact reactor vessel, a one-loop main cooling system and a simple fuel handling system is adopted enhancing cost reduction. For safety evaluation, reliability of the one-loop main cooling system has been shown by pipe-break transient analyses. Besides, construction cost of a demonstration plant with a first reactor and a small reprocessing and fuel fabrication facility is also evaluated. A major feature of the present concept is that the demonstration reactor and facilities can be directly appropriated for first commercial modules and the power plant can easily increase its capacity adding reactor and electrorefiner modules. A fast reactor cycle commercialization scenario using the present concept is thought to give low R&D or investment risk and high cost performance since the total demonstration plant cost is relatively small and the facilities are directly appropriated to commercial use.
Aizawa, Kosuke; Chikazawa, Yoshitaka; Usui, Shinichi; Konomura, Mamoru; Ando, Masato*
JAEA-Research 2007-042, 105 Pages, 2007/06
JAEA-Research-2007-042.pdf:3.64MB
Various conceptual design studies of sodium cooled small reactor have been performed in the feasibility study. In FY2005 study, a 300MWe modular reactor which adopts metal-fueled and 1 loop cooling system in order to pursues economical competitiveness was investigated. Transient analyses were performed to show core safety under the large pipe break accident that was found to be the severest accident in case of a 1 loop cooling system. From the analysis results, it was showed a possibility to maintain the core safety without the reactor scram. Transient analyses of the natural circulation decay heat removal system were also performed, and it was showed a possibility to maintain the core safety after the reactor scram. The in-vessel storage (IVS) was adopt to eliminate the ex-vessel storage and the design of the distribution flow adjustment device in IVS is studied. It was showed that the IVS could be introduced without modifying in the reactor design in FY2004. The rationalization of the fuel handling system is investigated taking advantage of co-location plant in which the reactor, the recycle plant and the fuel fabrication plant are co-located in a site. As a result of rationalization, the volume of the reactor building becomes 0.85 times as much as that of the design in FY2004.
Chikazawa, Yoshitaka; Okano, Yasushi; Konomura, Mamoru; Sato, Koji; Ando, Masato*; Nakanishi, Shigeyuki*; Sawa, Naoki*; Shimakawa, Yoshio*
Proceedings of 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) (CD-ROM), 8 Pages, 2006/06
A diversified or modular power source is attractive since it requires a low construction cost per unit and can be demonstrated in small scale experimental facilities. In this study, a new metal fuel sodium cooled reactor with 300MW electric has been developed enhancing cost reduction. And economical potential at demonstration stage with first of a kind (FOAK) is emphasized. A minimum configuration with a compact reactor vessel, a one-loop main cooling system and a simple fuel handling system are adopted enhancing cost reduction within safety requirement. Besides, construction cost of a demonstration plant with a first kind of reactor and a small reprocessing and fuel manufacturing facility is also evaluated. A major feature of the present concept is that the demonstration facilities can be appropriated for commercialized ones since they can be easily commercialize by increasing reactor and electrorefiner modules. A FBR cycle commercialization scenario using the present concept is thought to give low risk and high cost performance since the total demonstration plant cost is relatively small and the facilities are directly appropriated to commercial use.
Sakamoto, Yoshihiko; Kotake, Shoji; Nishikawa, Akira; Enuma, Yasuhiro; Ando, Masato; Sagayama, Yutaka
Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13), 0 Pages, 2005/05
The Feasibility Study on Commercialized Fast Reactor (FR) Cycle Systems is under way in order to propose prominent FR cycle systems that will respond to the diverse needs of society in the future. The design studies on various FR system concepts have been achieved and then the evaluations of potential to achieve the development targets have been carried out. Crucial issues have been found out for each FR system concept and their development plans for the key technologies are summarized as the roadmap. The characteristics and the differences in performances have been investigated. The crucial issues and the development periods have been clarified. Further investigation is now in progress. The promising concept will be proposed based on result of comparative evaluation at the end of the Phase II study.
Kotake, Shoji; Sakamoto, Yoshihiko; Enuma, Yasuhiro; Ando, Masato; Nishikawa, Akira; Sagayama, Yutaka
Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05), 0 Pages, 2005/05
The Feasibility Study on Commercialized Fast Reactor (FR) Cycle Systems is under way in order to propose prominent FR cycle systems that will respond to the diverse needs of society in the future. The design studies on various FR system concepts have been achieved and then the evaluations of potential to achieve the development targets have been carried out. Crucial issues have been found out for each FR system concept and their development plans for the key technologies are summarized as the roadmap. The characteristics and the differences in performances have been investigated. The crucial issues and the development periods have been clarified. Further investigation is now in progress. The promising concept will be proposed based on result of comparative evaluation at the end of the Phase II study.
Ono, Katsumi; masato, ando; Kotake, Shoji; Nagaoki, Yoshihiro; Namba, Takashi; Kato, Atsushi; Nakai, Ryodai; Negishi, Hitoshi
Nihon Genshiryoku Gakkai-Shi, 46(10), 685 Pages, 2004/10
A panoramic sensitivity analysis approach based on a statistic sampling method has been developed and applied for preliminary analysis on geological disposal of TRU waste considering variety of geological conditions and uncertainty. This approach can identify the parameters with the high importance for safety assessment and can extract the successful conditions for safety geological disposal.
Sakamoto, Yoshihiko; Sakamoto, Yoshihiko; Enuma, Yasuhiro; Ando, Masato; Nishikawa, Akira; Kotake, Shoji; Ieda, Yoshiaki
Dai-14-Kai Kantaiheiyo Genshiryoku Kaigi (2004-Nen 3-Gatsu 21-Nichi
25-Nichi), 0 Pages, 2003/00
This paper describes the summary of an interim report of phase II of the Feasibility Study on Commercialized FR Cycle Systems, related to reactor systems. Promising plant concepts (sodium-, lead-bismuth-, helium-, and water-cooled fast reactor) and reactor core concepts are presented. These concepts are quantitatively evaluated from the viewpoint of the suitability to the development targets, such as economic competitiveness, efficient utilization of resources and reduction of environmental burden, with securing safety. As results, sodium cooled fast reactor is well suited to the development targets. LBE cooled fast rector would have a potential to attain the development targets. Helium gas cooled fast reactor would have the great potential for high thermal efficiency and multipurpose energy system. And water cooled fast reactor has the advantage that there are many experiences with LWR. Furthermore the crucial issues for technical feasibility are also clarified as road map of key technology development for each concept.
Ogumo, Shinya*; Tsujita, Yoshihiro*; Ando, Masato; Hori, Toru*; Hayafune, Hiroki
no journal, ,
Methodology of Na/water reaction avoidance was studied by mechanically bonded double wall tubes and the inspection of both inner and outer tubes during plant periodical inspections term.
Chikazawa, Yoshitaka; Aizawa, Kosuke; Konomura, Mamoru; Shimakawa, Yoshio*; Sawa, Naoki*; Ando, Masato*
no journal, ,
no abstracts in English
Aizawa, Kosuke; Ando, Masato; Kotake, Shoji; Hayashi, Hideyuki; Hayafune, Hiroki; Fujii, Tadashi; Sato, Ikken; Kaito, Takeji
no journal, ,
no abstracts in English
Hagiwara, Hiroyuki*; Watanabe, Osamu*; Oyama, Kazuhiro*; Ando, Masato*; Ohshima, Hiroyuki; Yamano, Hidemasa
no journal, ,
Thermal hydraulic evaluation has been carried out for a pool-type sodium-cooled fast reactor to identify thermal hydraulic issues inside the reactor vessel which would be important in introducing the pool reactor. This study identified temperature change in the outer surface of the inner vessel in a reactor trip, natural convection of the reactor vessel wall cooling part in a full power operation, and cover-gas entrainment of the hot-pool free surface as important thermal hydraulic issues to be investigated in future.
Rekimoto, Masafumi; Ando, Masato; Chikazawa, Yoshitaka; Kato, Atsushi; Hamano, Tomoharu; Shiohama, Yasutaka; Miyagawa, Takayuki*; Uzawa, Masayuki*; Hara, Hiroyuki*; Yamauchi, Kanau*; et al.
no journal, ,
no abstracts in English
Rekimoto, Masafumi; Hamano, Tomoharu; Shiohama, Yasutaka; Ando, Masato*; Miyagawa, Takayuki*; Hara, Hiroyuki*; Yamauchi, Kanau*; Eda, Yuhei*; Koga, Kazuhiro*; Tanabe, Kenichi*
no journal, ,
no abstracts in English
Kato, Atsushi; Ichikawa, Kenta*; Nakata, Shuhei*; Chikazawa, Yoshitaka; Ando, Masato
no journal, ,
In the conceptual study of a tank-type sodium-cooled fast reactor, a decay heat removal system concept was developed, taking into account the use of natural circulation heat removal and the diversity of heat removal methods, and a basic plant operation way after the reactor trip was established.
Tokizaki, Minako*; Tani, Akihiro*; Ando, Masato*; Onoda, Yuichi
no journal, ,
Decay heat removal characteristics were evaluated for the Pool-Type Sodium-Cooled Fast Reactor (600 MWe class power) under the categories of Anticipated Operational Occurrences (AOO) and Design Basis Accidents (DBA), and it is expected that the integrity of the core fuel and coolant boundary can be ensured in light of the safety criteria. In addition, from the viewpoint of robustness confirmation of decay heat removal function, decay heat removal characteristics of immersion type DRACS during independent operation were evaluated, and the prospect of core cooling by natural circulation was obtained.
