• DocumentCode
    3147211
  • Title

    Generation IV SFR nuclear reactors: under-sodium repair for ASTRID

  • Author

    Baque, F. ; Chagnot, C. ; Bruguiere, L. ; Augem, J.M. ; Delalande, V. ; Sibilo, J.

  • Author_Institution
    CEA Nucl. Energy Div., Cadarache Centre, St. Paul-lez-Durance, France
  • fYear
    2013
  • fDate
    23-27 June 2013
  • Firstpage
    1
  • Lastpage
    7
  • Abstract
    For non-removable components of the future ASTRID prototype, repair operations will be performed in a gas environment. If the faulty area is located under the sodium free level, the gas-tight system will have to contain the inspection and repair tools and to protect them from the surrounding liquid sodium. Concerning repair tools, the unique laser tool has been selected for future SFRs: the repair scenario for in-sodium structures will first involve removing the sodium (after bulk draining), then machining and finally welding. Concerning conventional tools (brush or gas blower for sodium removal, milling machine for machining and TIG for welding for which its feasibility was demonstrated in the 1990s) are still considered as a back-up solution. In-pile examination or repair requires robotic carriers. These carriers have to be compatible with the sodium environment: either in the cover-gas plenum or in gas after sodium draining, or even under liquid sodium. This R&D programme has been divided into nine parts in order to provide an overall design of the required robotic carriers and to develop technological solutions for their components: detailed definition for SFR carrier needs (access to internal structures, possible defects to be detected/repaired), definition and specifications of carrier architecture (depending on inspection and repair scenarios), in-sodium leaktightness of carrier components, carrier material compatibility with sodium, temperature resistance (200°C), irradiation resistance (depending on the location of the main vessel), gas-tight bell for operations under liquid sodium, carrier positioning control in liquid sodium, development, validation and qualification of technological solutions, for future SFRs, and worldwide benchmark regarding the previous areas of investigation.
  • Keywords
    fission reactor operation; gas cooled reactors; robots; ASTRID prototype; gas environment; gas-tight system; generation IV SFR nuclear reactors; liquid sodium; sodium free level; Aging; Maintenance engineering; Materials; Resistance; Robots; Seals; Welding; ASTRID; Cleaning; ISI&R; LASER; Machining; Radiation; Repair; Robotics; SFR; Sodium; Temperature; Welding;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2013 3rd International Conference on
  • Conference_Location
    Marseille
  • Print_ISBN
    978-1-4799-1046-5
  • Type

    conf

  • DOI
    10.1109/ANIMMA.2013.6728036
  • Filename
    6728036