The Experts below are selected from a list of 246 Experts worldwide ranked by ideXlab platform

Nariaki Uto - One of the best experts on this subject based on the ideXlab platform.

  • A summary of sodium-cooled Fast Reactor development
    Progress in Nuclear Energy, 2014
    Co-Authors: Kazumi Aoto, Robert Hill, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Nariaki Uto
    Abstract:

    Abstract Much of the basic technology for the Sodium-cooled Fast Reactor (SFR) has been established through long term development experience with former Fast Reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.

  • design study and r d progress on japan sodium cooled Fast Reactor
    Journal of Nuclear Science and Technology, 2011
    Co-Authors: Kazumi Aoto, Nariaki Uto, Y Sakamoto, Mikio Toda, Takaya Ito, Shoji Kotake
    Abstract:

    This paper describes the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the “Fast Reactor Cycle Technology Development (FaCT)” project. A sodium-cooled Fast Reactor with an electric power of 1,500MWe is targeted for commercialization at around 2050, and a demonstration Reactor assuming a power output from 500 to 750MWe is planned to start operation at around 2025. R&D on innovative technologies to achieve economic competitiveness and enhance reliability and safety is carried out for the commercialization. A compact Reactor vessel without a vessel wall cooling system is pursued in consideration of the wall thickness enough to resist the severest seismic condition. A two-loop cooling system with shortened highchromium steel piping is a crucial feature, and studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being carried out. A double-walled straight tube steam generator is investigated to...

  • development of advanced loop type Fast Reactor in japan
    Nuclear Technology, 2010
    Co-Authors: Shoji Kotake, Kazumi Aoto, Nariaki Uto, Y Sakamoto, Takatsugu Mihara, Shigenobu Kubo, Yoshio Kamishima, Mikio Toda
    Abstract:

    This paper describes the current status of the design study and the related research and development for an advanced loop-type Fast Reactor: the Japan sodium-cooled Fast Reactor (JSFR). First, the development targets and the major design requirements are established. Then, a cost-down approach in which developing innovative technologies is key to being competitive with another future energy source is discussed. Here, the development status of several innovative technologies such as a two-loop cooling system, reliable Reactor system, simplified fuel-handling system, passive Reactor shutdown system, mitigation measure against a core disruptive accident, and minor actinide-bearing oxide fuel core is described. Last, a review of JSFR development and the demonstration plan for the innovative technologies are discussed.

Kazumi Aoto - One of the best experts on this subject based on the ideXlab platform.

  • A summary of sodium-cooled Fast Reactor development
    Progress in Nuclear Energy, 2014
    Co-Authors: Kazumi Aoto, Robert Hill, Philippe Dufour, Yang Hongyi, Jean Paul Glatz, Yeong-il Kim, Yury Ashurko, Nariaki Uto
    Abstract:

    Abstract Much of the basic technology for the Sodium-cooled Fast Reactor (SFR) has been established through long term development experience with former Fast Reactor programs, and is being confirmed by the Phenix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.

  • design study and r d progress on japan sodium cooled Fast Reactor
    Journal of Nuclear Science and Technology, 2011
    Co-Authors: Kazumi Aoto, Nariaki Uto, Y Sakamoto, Mikio Toda, Takaya Ito, Shoji Kotake
    Abstract:

    This paper describes the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the “Fast Reactor Cycle Technology Development (FaCT)” project. A sodium-cooled Fast Reactor with an electric power of 1,500MWe is targeted for commercialization at around 2050, and a demonstration Reactor assuming a power output from 500 to 750MWe is planned to start operation at around 2025. R&D on innovative technologies to achieve economic competitiveness and enhance reliability and safety is carried out for the commercialization. A compact Reactor vessel without a vessel wall cooling system is pursued in consideration of the wall thickness enough to resist the severest seismic condition. A two-loop cooling system with shortened highchromium steel piping is a crucial feature, and studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being carried out. A double-walled straight tube steam generator is investigated to...

  • development of advanced loop type Fast Reactor in japan
    Nuclear Technology, 2010
    Co-Authors: Shoji Kotake, Kazumi Aoto, Nariaki Uto, Y Sakamoto, Takatsugu Mihara, Shigenobu Kubo, Yoshio Kamishima, Mikio Toda
    Abstract:

    This paper describes the current status of the design study and the related research and development for an advanced loop-type Fast Reactor: the Japan sodium-cooled Fast Reactor (JSFR). First, the development targets and the major design requirements are established. Then, a cost-down approach in which developing innovative technologies is key to being competitive with another future energy source is discussed. Here, the development status of several innovative technologies such as a two-loop cooling system, reliable Reactor system, simplified fuel-handling system, passive Reactor shutdown system, mitigation measure against a core disruptive accident, and minor actinide-bearing oxide fuel core is described. Last, a review of JSFR development and the demonstration plan for the innovative technologies are discussed.

  • current status and perspective of advanced loop type Fast Reactor in Fast Reactor cycle technology development project
    2007
    Co-Authors: Hajime Niwa, Kazumi Aoto, Masaki Morishita
    Abstract:

    After selecting the combination of the sodium-cooled Fast Reactor (SFR) with oxide fuel, the advanced aqueous reprocessing and the simplified pelletizing fuel fabrication as the most promising concept of FR cycle system, 'Feasibility Study on Commercialized Fast Reactor Cycle Systems' was finalized in 2006. Instead, a new project, Fast Reactor Cycle Technology Development Project (FaCT Project) was launched in Japan focusing on development of the selected concepts. This paper describes the current status and perspective of the advanced loop type SFR system in the FaCT Project, especially on the design requirements, current design as well as the related innovative technologies together with the development road-map. Some considerations on advantages of the advanced loop type design are also described. (authors)

Shoji Kotake - One of the best experts on this subject based on the ideXlab platform.

  • design study and r d progress on japan sodium cooled Fast Reactor
    Journal of Nuclear Science and Technology, 2011
    Co-Authors: Kazumi Aoto, Nariaki Uto, Y Sakamoto, Mikio Toda, Takaya Ito, Shoji Kotake
    Abstract:

    This paper describes the progress of the design study and research and development (R&D) for the Japan Sodium-cooled Fast Reactor (JSFR) implemented in the “Fast Reactor Cycle Technology Development (FaCT)” project. A sodium-cooled Fast Reactor with an electric power of 1,500MWe is targeted for commercialization at around 2050, and a demonstration Reactor assuming a power output from 500 to 750MWe is planned to start operation at around 2025. R&D on innovative technologies to achieve economic competitiveness and enhance reliability and safety is carried out for the commercialization. A compact Reactor vessel without a vessel wall cooling system is pursued in consideration of the wall thickness enough to resist the severest seismic condition. A two-loop cooling system with shortened highchromium steel piping is a crucial feature, and studies on the hydraulics in the pipe elbow and the fabrication capability of the pipes are being carried out. A double-walled straight tube steam generator is investigated to...

  • development of advanced loop type Fast Reactor in japan
    Nuclear Technology, 2010
    Co-Authors: Shoji Kotake, Kazumi Aoto, Nariaki Uto, Y Sakamoto, Takatsugu Mihara, Shigenobu Kubo, Yoshio Kamishima, Mikio Toda
    Abstract:

    This paper describes the current status of the design study and the related research and development for an advanced loop-type Fast Reactor: the Japan sodium-cooled Fast Reactor (JSFR). First, the development targets and the major design requirements are established. Then, a cost-down approach in which developing innovative technologies is key to being competitive with another future energy source is discussed. Here, the development status of several innovative technologies such as a two-loop cooling system, reliable Reactor system, simplified fuel-handling system, passive Reactor shutdown system, mitigation measure against a core disruptive accident, and minor actinide-bearing oxide fuel core is described. Last, a review of JSFR development and the demonstration plan for the innovative technologies are discussed.

  • a next generation sodium cooled Fast Reactor concept and its r d program
    Nuclear Engineering and Technology, 2007
    Co-Authors: Masakazu Ichimiya, Tomoyasu Mizuno, Shoji Kotake
    Abstract:

    Critical issues in the development targets for the future Fast Reactor(FR) cycle system, including sodium-cooled FR were to ensure safety assurance, efficient utilization of resources, reduction of environmental burden, assurance of nuclear non-proliferation, and economic competitiveness. A promising design concept of sodium-cooled Fast Reactor JSFR is proposed aiming at fully satisfaction of the development targets for the next generation nuclear energy system. A roadmap toward JSFR commercialization is described, to be followed up in a new framework of the Fast Reactor Cycle Technology development(FaCT) Project launched in 2006.

Pierre Lo Pinto - One of the best experts on this subject based on the ideXlab platform.

  • a case for small modular Fast Reactor
    Journal of Nuclear Science and Technology, 2007
    Co-Authors: Y I Chang, Mamoru Konomura, Pierre Lo Pinto
    Abstract:

    This paper describes a 50MWe Small Modular Fast Reactor (SMFR) design that has been developed jointly by Argonne National Laboratory (ANL), Commissariat a l'Energie Atomique (CEA), and Japan Atomic Energy Agency (JAEA) as an international collaborative effort. Key design innovations include a metallic fueled core with 30-year lifetime and supercritical carbon dioxide Brayton cycle.

Y I Chang - One of the best experts on this subject based on the ideXlab platform.

  • a case for small modular Fast Reactor
    Journal of Nuclear Science and Technology, 2007
    Co-Authors: Y I Chang, Mamoru Konomura, Pierre Lo Pinto
    Abstract:

    This paper describes a 50MWe Small Modular Fast Reactor (SMFR) design that has been developed jointly by Argonne National Laboratory (ANL), Commissariat a l'Energie Atomique (CEA), and Japan Atomic Energy Agency (JAEA) as an international collaborative effort. Key design innovations include a metallic fueled core with 30-year lifetime and supercritical carbon dioxide Brayton cycle.