Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 25

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Evaluation of JSFR key technologies

Chikazawa, Yoshitaka; Aoto, Kazumi; Hayafune, Hiroki; Kotake, Shoji; Ono, Yushi; Ito, Takaya*; Toda, Mikio*

Nuclear Technology, 179(3), p.360 - 373, 2012/09

 Times Cited Count:9 Percentile:62.49(Nuclear Science & Technology)

Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) have been evaluated. The ten technologies: high burn-up fuel, safety enhancement, compact reactor vessel, two-loop cooling system using high chromium steel, integrated intermediate heat exchanger/pump component, reliable steam generator, natural circulation decay heat removal system, simplified fuel handling system, containment vessel made of steel plate reinforced concrete and advanced seismic isolation system have been confirmed to be feasible to be installed a conceptual design of demonstration JSFR to be ready for large scale demonstration experiments.

Journal Articles

JSFR design study and R&D progress in the FaCT project

Aoto, Kazumi; Uto, Nariaki; Sakamoto, Yoshihiko; Ito, Takaya*; Toda, Mikio*; Kotake, Shoji*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 11 Pages, 2012/00

In the FaCT project, SFR with 1,500 MWe is a target for the commercialization. R&D on innovative technologies to achieve the economic competitiveness and enhance the reliability and safety is carried out. A compact RV without wall-cooling layer is pursued in consideration of seismic reliability. For a two-loop cooling system with shortened high chromium steel piping, studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being performed. A double-walled straight tube SG is investigated to enhance the reliability against sodium/water reaction, and developmental works are progressing including the thermal-hydraulic design and trial manufacturing for components. SASS is being developed with safety analysis of the applicability for JSFR and experimental demonstration in JOYO. An advanced fuel handling system is also pursued. Discussion on whether the innovative technologies can be adopted for JSFR is in progress to be finalized in 2010.

Journal Articles

Conceptual design for a large-scale Japan sodium-cooled fast reactor, 1; Feasibility of key technologies

Chikazawa, Yoshitaka; Aoto, Kazumi; Hayafune, Hiroki; Ono, Yushi; Kotake, Shoji; Toda, Mikio*; Ito, Takaya*

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), p.426 - 435, 2011/05

Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) has been evaluated. The hot vessel, two-loop cooling system using high chromium steel, integrated intermediate heat exchanger/pump component, highly reliable steam generator, natural circulation decay heat removal system and improved in-service inspection and repair capability have been confirmed to be feasible as development items for the next stage.

Journal Articles

Design study and R&D progress on Japan sodium-cooled fast reactor

Aoto, Kazumi; Uto, Nariaki; Sakamoto, Yoshihiko; Ito, Takaya*; Toda, Mikio*; Kotake, Shoji*

Journal of Nuclear Science and Technology, 48(4), p.463 - 471, 2011/04

In the FaCT project, SFR with 1,500 MWe is a target for the commercialization. R&D on innovative technologies to achieve the economic competitiveness and enhance the reliability and safety is carried out. A compact RV without wall-cooling layer is pursued in consideration of seismic reliability. For a two-loop cooling system with shortened high chromium steel piping, studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being performed. A double-walled straight tube SG is investigated to enhance the reliability against sodium/water reaction, and developmental works are progressing including the thermal-hydraulic design and trial manufacturing for components. SASS is being developed with safety analysis of the applicability for JSFR and experimental demonstration in JOYO. An advanced fuel handling system is also pursued. Discussion on whether the innovative technologies can be adopted for JSFR is in progress to be finalized in 2010.

Journal Articles

Development of advanced loop-type fast reactor in Japan; Progress of design study based on preliminary assessment results

Sakamoto, Yoshihiko; Kotake, Shoji; Aoto, Kazumi; Toda, Mikio*

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 9 Pages, 2010/05

JAEA is now performing a FaCT project. The first milestone is in 2010; decisions about whether or not to adopt innovative technologies in the JSFR design will be made in the year. Preliminary assessment is underway to produce recommendations for final discussion. This paper describes some important progress in the preliminary assessment. As for the reactor system design, structural integrity against both thermal stress and seismic force was investigated. Then, the specification of the reactor system was established. Also, investigation of design options to extend a design margin against seismic force has been suggested. Regarding thermal hydraulics issues, design measures have been introduced to restrain cover gas entrainment and vortex cavitations. Further investigation is now in progress for design optimization or improvement of preventive effect. Concerning the piping design of primary cooling circuit, the creep strength reduction by Type-IV damage was taken into account.

Journal Articles

Development of advanced loop-type fast reactor in Japan

Kotake, Shoji; Sakamoto, Yoshihiko; Mihara, Takatsugu; Kubo, Shigenobu*; Uto, Nariaki; Kamishima, Yoshio*; Aoto, Kazumi; Toda, Mikio*

Nuclear Technology, 170(1), p.133 - 147, 2010/04

 Times Cited Count:33 Percentile:91.95(Nuclear Science & Technology)

Japan Atomic Energy Agency (JAEA) is now executing "Fast Reactor Cycle Technology Development (FaCT)" project in cooperation with the Japanese electric utilities. In the FaCT project, both the conceptual design study for Japan Sodium-cooled Fast Reactor (JSFR) and the developments of innovative technologies to be adopted to JSFR are now implemented with paying attention to the consistency between the design and the innovative technologies. The current target is that the development will be accomplished around 2015, after that a licensing procedure for the demonstration JSFR will be launched. This paper describes design requirements, design characteristics of JSFR and evaluation on the performances for economic competitiveness. Furthermore, the current status of the key technology development for JSFR is briefly introduced.

Journal Articles

Conceptual design for Japan Sodium-cooled Fast Reactor, 1; Current status of system design for JSFR

Uto, Nariaki; Sakai, Takaaki; Mihara, Takatsugu; Toda, Mikio*; Kotake, Shoji; Aoto, Kazumi

Proceedings of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09) (CD-ROM), p.9298_1 - 9298_11, 2009/05

A conceptual design for JSFR and developments of innovative technologies are implemented. A compact RV has been designed to enhance the economy. The regarding development results have been reflected to the RV design. An innovative CV design has been implemented with elemental tests to reduce the construction cost. SASS and the NC DHRS have been designed to enhance the safety, with the irradiation data acquired in Joyo and the development of a 3-dimensional thermal-hydraulic evaluation method. An approach for ISI/R has been provided to be applicable for FR characteristics, and the developmental studies on innovative inspection technologies have been progressed. Other technologies including double-walled pipes with short elbows, a pump-integrated IHX are also being developed. These results, together with a preliminary conceptual design study on a demonstrative reactor for JSFR, will be utilized as resources in 2010 to determine which innovative technologies should be adopted.

Journal Articles

Development of advanced loop-type fast reactor in Japan, 1; Current status of JSFR development

Kotake, Shoji; Mihara, Takatsugu; Kubo, Shigenobu; Aoto, Kazumi; Toda, Mikio*

Proceedings of 2008 International Congress on Advances in Nuclear Power Plants (ICAPP '08) (CD-ROM), p.486 - 495, 2008/06

Japan Atomic Energy Agency (JAEA) is now executing "Fast Reactor Cycle Technology Development (FaCT)" project in cooperation with the Japanese electric utilities. In the FaCT project, both the conceptual design study for JAEA sodium-cooled fast reactor (JSFR) and the developments of the innovative technologies are now implemented with paying attention to the consistency between the design and the innovative technologies. The current target is that the development will have been accomplished around 2015, after that a licensing procedure for JSFR demonstration reactor will be launched. This paper describes the design requirements, design characteristics of JSFR and evaluation on the performances for economic competitiveness. Furthermore, the current status of the key technology development for JSFR is briefly introduced.

Journal Articles

Progress on the plant design concept of sodium-cooled fast reactor

Hishida, Masahiko*; Kubo, Shigenobu; Konomura, Mamoru; Toda, Mikio*

Journal of Nuclear Science and Technology, 44(3), p.303 - 308, 2007/03

 Times Cited Count:16 Percentile:74.96(Nuclear Science & Technology)

An innovative concept of sodium-cooled fast reactor, named JNC Sodium Cooled FR (JSFR) has been created and modified through the Feasibility Study on Commercialized FR Cycle System, aiming at full satisfaction of the development targets. A modified concept of JSFR applied double-wall straight tube type steam generator (SG) which is excelling in safety for sodium-water reaction has been developed. In addition, decay heat removal system suitable for the straight tube SG has been selected and in-service inspection and repair capabilities have been improved. As the result of this study, the potential to realize this plant concept has been obtained through evaluation concerning safety and economics.

Journal Articles

Mitsubishi activities for advanced reactor development; Sodium-cooled Fast Reactor

Ito, Takaya*; Sato, Hiroyuki*; Usui, Yukinori*; Toda, Mikio*

Mitsubishi Juko Giho, 43(4), p.45 - 49, 2006/12

MHI has participated in the FBR development that is a national project from an initial stage as a member of fabricators. Aiming at FBR commercialization until 2050, MHI has actively contributed to "Feasibility Studies on Commercialized Fast Reactor Cycle System" performed mainly by JAEA from 1999. This time, the Sodium-cooled Fast Reactor was chosen at a national level as the main concept. This Sodium-cooled Fast Reactor is proposed by MHI, and for an economy improvement innovation technologies (reduction of the number of the loops, shortening of piping systems, integrated IHX/Pump component and so on) are adopted in this concept. From now on, research and development for FBR commercialization will be accelerated at a national level toward realization of a demonstration reactor until about 2025. MHI also challenges the project as a proposer of this concept.

Journal Articles

Development of a slim manipulator type fuel handling machine for a commercialized fast reactor

Chikazawa, Yoshitaka; Usui, Shinichi; Konomura, Mamoru; Sadahiro, Daisuke*; Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Kotake, Shoji*

Proceedings of 14th International Conference on Nuclear Engineering (ICONE-14) (CD-ROM), 7 Pages, 2006/07

A seismic analysis has been performed showing that the seismic interaction between the UIS and the FHM can be avoided adopting gapless bearings at the FHM arm joint. An angular contact ball bearing is suitable for the new FHM since it can eliminate gaps by preload pressure. A major problem of the FHM bearings is lubrication since the contact pressure between steel rings and ball increases because of ball bearing. Additionally, FHM operating temperature is about 200 deg-C and normal grease is not applicable under argon gas with sodium vapor. A endurance test with 1/10 scale bearings in the air has been performed to show applicability of angular contact ball bearings to the FHM arm joint. The results with 20,000 cycle showed that bearings with combination of MoS$$_{2}$$ coating steel rings and ceramics balls can be tolerable as the FHM operating condition. A real scale bearing test in argon gas with sodium vapor has also been demonstrated to reveal bearing size and sodium vapor effects.

Journal Articles

Progress on the plant design concept of sodium-cooled fast reactor

Hishida, Masahiko; Murakami, Tsutomu; Konomura, Mamoru; Toda, Mikio*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 6 Pages, 2005/10

An innovative concept of sodium-cooled fast reactor, named JNC Sodium Cooled FR (JSFR) has been created and modified through the Feasibility Study on Commercialized FR Cycle System, aiming at full satisfaction of the development targets. A modified concept of JSFR applied double-wall straight tube type steam generator (SG) which is excelling in safety for sodium-water reaction has been developed. In addition, decay heat removal system suitable for the straight tube SG has been selected and in-service inspection and repair capabilities have been improved. As the result of this study, the potential to realize this plant concept has been obtained through evaluation concerning safety and economics.

Journal Articles

Thermal-hydraulic design concerning reactor upper plenum and large diameter piping for the innovative sodium-cooled fast reactor

Fujii, Tadashi; Konomura, Mamoru; Kamide, Hideki; Yamaguchi, Akira; Toda, Mikio*

Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13), 0 Pages, 2005/05

An innovative sodium-cooled fast reactor (JSFR) has been investigated on the Feasibility Study on Commercialized Fast Reactor (FR) Cycle Systems. In order to reduce plant construction cost, JSFR adopts compacted reactor vessel and reduction of loop number. According to adoption of compacted cooling system, sodium flow velocities in the reactor upper plenum and the pipings of the cooling system exceed to those of conventional design, therefore, flow optimization in the reactor upper plenum and structural integrity of the piping system to flow-induced vibration (FIV) have been actualized as thermal-hydraulic issues. To solve above issues, some water experiments have been performed. The thermal-hydraulic design of the primary cooling system including the reactor vessel has been advanced reflecting these experimental results.

Journal Articles

LMFBR Design and its Evolution, 4; An Innovative Concept of Sodium-Cooled Middle-Scale Modular Reactor Pursuing High Economic Competitiveness

; ; Konomura, Mamoru; Toda, Mikio*

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (Internet), 8 Pages, 2003/00

None

Oral presentation

Development of an fuel handling system for commercialized fast breeder reactor, 1; Conceptual design of fuel handling system

Usui, Shinichi; Chikazawa, Yoshitaka; Konomura, Mamoru; Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Ikeda, Hirotsugu

no journal, , 

no abstracts in English

Oral presentation

Development of an fuel handling system for commercialized fast breeder reactor, 2; Conceptual design of in-vessel fuel handling system

Chikazawa, Yoshitaka; Konomura, Mamoru; Usui, Shinichi; Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Ikeda, Hirotsugu*

no journal, , 

no abstracts in English

Oral presentation

Concept study on fuel handling system of commercialized sodium cooled reactor, 3; Study on ex-vessel sodium storage facility

Hori, Toru*; Tozawa, Katsuhiro*; Toda, Mikio*; Chikazawa, Yoshitaka; Usui, Shinichi; Ikeda, Hirotsugu*

no journal, , 

no abstracts in English

Oral presentation

Concept study on fuel handling system of commercialized sodium cooled reactor, 4; Study on spent fuel cleaning and water loading system

Tozawa, Katsuhiro*; Hori, Toru*; Toda, Mikio*; Chikazawa, Yoshitaka; Usui, Shinichi; Ikeda, Hirotsugu*

no journal, , 

no abstracts in English

Oral presentation

Study on chemical reactivity control of liquid sodium, 1; Research program of project

Ara, Kuniaki; Saito, Junichi; Sugiyama, Kenichiro*; Kitagawa, Hiroshi*; Ogata, Hiroshi*; Toda, Mikio*; Yoshioka, Naoki*

no journal, , 

no abstracts in English

Oral presentation

Study on chemical reactivity control of liquid sodium, 3; Preliminary feasibility study of nano-fluid to FBR plant

Ichikawa, Kenta*; Ara, Kuniaki; Saito, Junichi; Toda, Mikio*; Yoshioka, Naoki*

no journal, , 

no abstracts in English

25 (Records 1-20 displayed on this page)