Progress on the Plant Design Concept of Sodium-Cooled Fast Reactor

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概要

• 論文の詳細を見る

• An innovative concept of sodium-cooled fast reactor, named JAEA 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.

• 社団法人 日本原子力学会の論文
• 2007-03-25

著者

• Kubo Shigenobu

  Japan Atomic Power Company

• HISHIDA Masahiko

  Japan Atomic Energy Agency (JAEA)

• KONOMURA Mamoru

  Japan Atomic Energy Agency (JAEA)

• TODA Mikio

  Mitsubishi Heavy Industries, LTD.

• Toda Mikio

  Mitsubishi Heavy Industries Ltd.

• Konomura Mamoru

  Japan Atomic Energy Agency

• Toda Mikio

  Mitsubishi Fbr Systems Inc.

関連論文

• Progress on the Plant Design Concept of Sodium-Cooled Fast Reactor
• Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident
• ICONE11-36598 Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor
• Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident
• Design Study and R&D Progress on Japan Sodium-Cooled Fast Reactor
• A Case for Small Modular Fast Reactor

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