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Journal Articles

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

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.

Journal Articles

A Conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

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.

Journal Articles

Design study for reactor system of fast reactor JSFR; Concept of reactor system

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.

Journal Articles

JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 3; Progress of component design

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.

Journal Articles

Seismic PRA for Japan Sodium-cooled Fast Reactor (JSFR)

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

Journal Articles

Thermal-hydraulic studies on self actuated shutdown system for Japan Sodium-cooled Fast Reactor

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.

Journal Articles

Development of a self actuated shutdown system for large sacle JSFR

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

Journal Articles

Conceptual design study of JSFR, 2; Reactor system

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.

Journal Articles

Seismic isolation design for JSFR

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.

Journal Articles

Development of a small specimen test machine to evaluate irradiation embrittlement of fusion reactor materials

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:10 Percentile:58.49(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Post-irradiation fatigue test of 21/4Cr-1Mo steel for the pressure vessel material of the HTTR

; 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

JAEA Reports

Development of a remote controlled fatigue testing apparatus at elevated temperature in controlled environment

Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;

JAERI-Tech 96-005, 39 Pages, 1996/02

JAERI-Tech-96-005.pdf:2.28MB

no abstracts in English

Journal Articles

Post irradiation examinations on HTTR materials

; Omi, Masao; Eto, Motokuni; Watanabe, Katsutoshi

KAERI-NEMAC/TR-32/95, 0, p.282 - 295, 1995/00

no abstracts in English

Oral presentation

Conceptual design toward the commercial reactor of JSFR, 4; Reactor system

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.

Oral presentation

Analysis of temperature response characteristics for coolant around SASS sensitive alloy in demonstration FBR

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.

Oral presentation

A Conceptual design study of the demonstration fast breeder reactor for enhancement of maintenance and repair capability, 2; Design improvement of reactor structure

Isono, Kenichi; Chikazawa, Yoshitaka; Dozaki, Koji*; Kawasaki, Nobuchika*; Eto, Masao*

no journal, , 

no abstracts in English

Oral presentation

Seismic PRA for Japan Sodium-cooled Fast Reactor (JSFR)

Naruto, Kenichi*; Nishino, Hiroyuki; Kurisaka, Kenichi; Yamano, Hidemasa; Okano, Yasushi; Okamura, Shigeki*; Eto, Masao*

no journal, , 

no abstracts in English

Oral presentation

A Conceptual design study of the demonstration fast breeder reactor for enhancement of maintenance and repair capability, 4; Design improvement of reactor structure

Isono, Kenichi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Dozaki, Koji*; Kawasaki, Nobuchika*; Eto, Masao*

no journal, , 

no abstracts in English

Oral presentation

Design study for reactor system of fast reactor JSFR, 1; Concept of reactor system

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.

Oral presentation

Design study for reactor system of fast reactor JSFR, 2; Aseismic study of the column type UIS with a slit

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.

24 (Records 1-20 displayed on this page)