%0 Journal Article
%T Development of Tools, Instrumentation and Codes for Improving Periodic Examination and Repair of SFRs
%A Fran£¿ois Baqu¨¦
%A Fr¨¦d¨¦ric Reverdy
%A Jean-Michel Augem
%A Julien Sibilo
%J Science and Technology of Nuclear Installations
%D 2012
%I Hindawi Publishing Corporation
%R 10.1155/2012/718034
%X In the frame of the CEA, EDF, and AREVA coordinated research program launched in 2007 for the development of Generation IV sodium-cooled fast reactors (SFRs), the improvement of in-service inspection and repair (ISI&R) capabilities was identified as a major issue. Within the French-associated multiannual SFR research program, the periodic examination and repair are looked at through the following main R&D axes: (i) improvement of the primary system conceptual design in order to ease periodic examination and repair, (ii) development of inspection techniques (periodic inspection tools and associated simulation), (iii) accessibility and associated robotics, and (iv) development and validation of repair processes. Associated needs are being defined through an iterative method between designers and inspection specialists: adaptation of the SFR design to ISI&R requirements, validation of the ultrasonic transducers, of associated ultrasonic nondestructive examination techniques, of laser repair processes, of associated robotic equipment. International collaboration is also running for some specific items such as ultrasonic visualization under liquid sodium. 1. Introduction From within the framework of the French Act, dated June 28, 2006, which requests an assessment of the industrial perspectives of transmutation by 2012, the Generation IV systems, especially the sodium-cooled fast reactors seem to be the most mature technology to be developed among the systems proposed for sustainable energy. Thus, since 2007, the CEA, EDF, and AREVA French partners launched a coordinated research program on sodium cooled fast reactors (SFR), which is now being used for the next ASTRID (advanced sodium technological reactor for industrial demonstration) prototype [1]. These program main axes were classified into four R&D items:(1)design of a core with enhanced safety;(2)better resistance of SFRs to severe accidents and external hazards;(3)research on an optimized energy conversion system to reduce the sodium risk;(4)review of reactor and component design options in order to:(i)improve inspection, maintenance, availability, and decommissioning; (ii)reduce the environmental impact while reinforcing resistance to proliferation; (iii)improve the reactor performance and overall economic aspect. Among these items, improvement of in-service inspection and repair (ISI&R) is a major transverse issue [2]. ISI&R is strongly linked to safety analysis (the three defense lines: checking the state of material and equipment during the reactor¡¯s life span, detection of premature failures, and
%U http://www.hindawi.com/journals/stni/2012/718034/