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Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.
Mechanical Engineering Journal (Internet), 7(3), p.19-00489_1 - 19-00489_16, 2020/06
The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.
Kubo, Shigenobu; Chikazawa, Yoshitaka; Ohshima, Hiroyuki; Uchita, Masato*; Miyagawa, Takayuki*; Eto, Masao*; Suzuno, Tetsuji*; Matoba, Ichiyo*; Endo, Junji*; Watanabe, Osamu*; et al.
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
The authors are developing the design concept of pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDGs) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident.
Kawasaki, Nobuchika; Sakamoto, Yoshihiko; Eto, Masao*; Taniguchi, Yoshihiro*; Kamishima, Yoshio*
Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), p.760 - 769, 2015/05
The Japan Sodium-cooled Fast Reactor, JSFR, is currently under conceptual study. The concept of JSFR's reactor system is a compact reactor system to avoid excessive increase of reactor vessel diameter with structural and fluid integrities. To realize this concept, single rotating plug with advanced refueling system is adopted. Advanced refueling system consists of column type Upper Internal Structure and pantograph type Fuel Handling Machine. To realize structural and fluid integrities, top entry piping, sodium dam and flow block/guide structures are adopted. Structural integrities against seismic displacement or thermal stress and fluid integrities against vortex cavitations or cover gas entrainment can be ensured with these designs.
Enuma, Yasuhiro; Kawasaki, Nobuchika; Orita, Junichi*; Eto, Masao*; Miyagawa, Takayuki*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05
In the frame work of generation IV international forum, safety design criteria and safety design guideline for the generation IV sodium-cooled fast reactors have been developing. JAEA, JAPC, MFBR have been investigating design study for JSFR to satisfy SDC. In addition to the safety measures, maintainability, reparability and manufacturability are taken into account in the JSFR design study. This paper describes the design of main components. Enlargement of the access route for the inspection devices and addition of the access routes were carried out for the reactor structure. The pump-integrated IHX was modified for the primary heat exchanger, which was installed for the decay heat removal in the IHX at the upper plenum, to be removable for improved repair and maintenance. For the steam generator, protective wall tube type design is under investigation as an option with less R&D risks.
Naruto, Kenichi*; Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa; Okano, Yasushi; Okamura, Shigeki*; Eto, Masao*
Proceedings of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9) (CD-ROM), 10 Pages, 2014/11
Hagiwara, Hiroyuki; Yamada, Yumi*; Eto, Masao*; Oyama, Kazuhiro*; Watanabe, Osamu*; Yamano, Hidemasa
Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 8 Pages, 2012/12
The self-actuated shutdown system (SASS), which is selected for Japan Sodium-cooled Fast Reactor (JSFR), is a passive reactor shutdown system utilizing a Curie point electromagnet (CPEM). With CPEM, an excessive fuel outlet temperature rise is sensed and the control rods are released into the core, and the reactor can be shutdown. Therefore it is important for feasibility of SASS to be established by assuring a quick response of CPEM to the coolant temperature rise. In this paper, a device named "flow collector", which collects flows discharged from six fuel subassemblies surrounding CPEM backup control rods, has been proposed to ensure a shorter response time.
Fujita, Kaoru; Yamano, Hidemasa; Kubo, Shigenobu*; Eto, Masao*; Yamada, Yumi*; Toyoshi, Akira*
Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 6 Pages, 2012/12
no abstracts in English
Okamura, Shigeki*; Eto, Masao*; Kamishima, Yoshio*; Negishi, Kazuo; Sakamoto, Yoshihiko; Kitamura, Seiji; Kotake, Shoji*
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 10 Pages, 2012/00
This paper describes the seismic design of JSFR, which includes the seismic condition, the seismic isolation system and the seismic evaluation of primary component. JSFR employs a seismic isolation system to mitigate the earthquake force. The design seismic loading is made more severe than ever since Niigata-ken Chuetsu-oki Earthquake in 2007. The earthquake force loaded on the primary components has to be mitigated more than that of the previous seismic isolation system. We examined the advanced seismic isolation system by optimizing the performance of the previous seismic isolation system considering the natural frequency of the primary components. The advanced seismic isolation system for SFR was adopted laminated rubber bearings which are thicker than that of the previous, as well as oil dampers. The seismic evaluation of nuclear reactor components under applying the advanced seismic isolation system was performed; the performance of the system was confirmed.
Eto, Masao*; Kamishima, Yoshio*; Okamura, Shigeki*; Watanabe, Osamu*; Oyama, Kazuhiro*; Negishi, Kazuo; Kotake, Shoji*; Sakamoto, Yoshihiko; Kamide, Hideki
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 10 Pages, 2012/00
In the JSFR design, the diameter of the Reactor Vessel (RV) shall be minimized and the reactor internal structures shall be simplified for reduction in construction cost. The reduction in the RV diameter is achieved by adopting an advanced refueling system and the hot RV with high temperature wall. The flow velocity in the reactor upper plenum increases because the diameter of the RV is decreased. As the result, the coolant flow field in reactor upper plenum is severe. The optimization of the coolant flow field in the reactor upper plenum was carried out for prevention the cover gas entrainment and the vortex cavitations at the hot leg intake. In addition, structural integrities for seismic loadings and thermal loadings were evaluated because the design seismic loading was highly increased and the vessel wall is directly exposed to the thermal transients of the upper plenum. This paper describes the characteristics and the results of the design study of the reactor system.
Ishii, Toshimitsu; Omi, Masao; Saito, Junichi; Hoshiya, Taiji; Ooka, Norikazu; Jitsukawa, Shiro; Eto, Motokuni
Journal of Nuclear Materials, 283-287(Part.2), p.1023 - 1027, 2000/12
Times Cited Count：12 Percentile：61.88(Materials Science, Multidisciplinary)no abstracts in English
; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu
JAERI-Research 96-028, 33 Pages, 1996/06
JAERI-Research-96-028.pdf:1.85MB
no abstracts in English
Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;
JAERI-Tech 96-005, 39 Pages, 1996/02
no abstracts in English
; Omi, Masao; Eto, Motokuni; Watanabe, Katsutoshi
KAERI-NEMAC/TR-32/95, 0, p.282 - 295, 1995/00
no abstracts in English
Hagiwara, Hiroyuki*; Oyama, Kazuhiro*; Watanabe, Osamu*; Eto, Masao*; Yamano, Hidemasa
no journal, ,
Fast Reactor Cycle Technology Development Project (FaCT) adopts Self-Actuated Shutdown System (SASS). SASS is the system dropping the control rod to shutdown by sensing the core outlet temperature rise from Anticipated Transient Without Scram (ATWS) of abnormal transition. Hence, coolant flow velocity around the SASS sensing alloy improves temperature response time constant. Especially, accelerating the coolant flow velocity in the slit installed at the SASS sensing alloy. This study aims at flow acceleration and considers proposed structure of incorporating flow collector surrounding six SASS auxiliary assembly. The result of the effectiveness evaluation by three-dimensional thermal hydraulic analyses is presented.
Isono, Kenichi; Chikazawa, Yoshitaka; Dozaki, Koji*; Kawasaki, Nobuchika*; Eto, Masao*
no journal, ,
no abstracts in English
Kawasaki, Nobuchika; Sakamoto, Yoshihiko; Eto, Masao*; Taniguchi, Yoshihiro*; Kamishima, Yoshio*
no journal, ,
As design study for reactor system of fast reactor JSFR, concept of reactor system and development issues are introduced.
Eto, Masao*; Kamishima, Yoshio*; Kawasaki, Nobuchika; Sakamoto, Yoshihiko; Noi, Hiromi*
no journal, ,
As design study for reactor system of fast reactor JSFR, aseismic study of the column type UIS with a slit is performed.
Chikazawa, Yoshitaka; Kubo, Shigenobu; Miyagawa, Takayuki*; Eto, Masao*
no journal, ,
Thermal transient on reactor vessel around sodium surface in a pool type reactor has been evaluated. Taking into account severe earthquake conditions, thickness of the reactor vessel is increased from the original design. Thermal transient evaluation including creep fatigue and ratchet at the sodium surface have been evaluated on that improved reactor vessel design against seismic load.
Chikazawa, Yoshitaka; Aizawa, Kosuke; Kato, Atsushi; Eto, Masao*; Matsunaga, Shoko*
no journal, ,
A next generation sodium cooled reactor introduce a flexible arm fuel handling machine to reduce reactor vessel diameter. In this study, prevention of jamming at the movable parts of the fuel handling machine and recovery from jamming is investigated.
Eto, Masao*; Kamishima, Yoshio*; Okamura, Shigeki*; Negishi, Kazuo*; Sakamoto, Yoshihiko; Kawasaki, Nobuchika
no journal, ,
A concept of a compact reactor system for Japan Sodium-cooled Fast Reactor (JSFR) is being studied with aims including streamlining its facilities. A candidate of innovative technology for this purpose is a fuel exchange system which consists of an upper internal structure (UIS) with a radial slit and a single rotating plug, and another candidate is a "ot vessel" concept. The applicability of this structural concept has been studied by considering flow optimization, seismic resistance, thermal evaluation, etc. This paper reports the result of the applicability study.
