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
Link To Document :
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