DocumentCode :
1587959
Title :
ASTRID sodium cooled fast reactor: Program for improving in service inspection and repair
Author :
Jadot, F. ; Baqué, F. ; Jeannot, J. Ph ; de Dinechin, G. ; Augem, J.M. ; Sibilo, J.
Author_Institution :
DER, ASTRID Plant Project, St. Paul-lez-Durance, France
fYear :
2011
Firstpage :
1
Lastpage :
8
Abstract :
In the frame of the CEA, EDF, AREVA coordinated research program for the development of Generation IV sodium-cooled fast reactors (SFR), the ASTRID project was launched in 2010. For the future prototype, the improvement of in-service inspection and repair (ISI&R) capabilities was identified as a major issue. Following the pluriannual SFR research program, the ISI&R main R&D axes remain: i) improvement of the primary system conceptual design, ii) development of measurement and inspection techniques (continuous monitoring instrumentation and periodic inspection tools), iii) accessibility and associated robotics, and iv) development and validation of repair processes. Associated ISI&R needs are being defined through an iterative method between designers and instrumentation specialists : adaptation of the Design to ISI&R requirements, fission chamber development, validation of the ultrasonic and chemical transducers, of ultrasonic non destructive simulation, of acoustic surveillance, of laser repair intervention processes, of connected robotic equipment. Moreover, CEA, as leader of the ASTRID Project, is willing to find new contributors, partners or suppliers, in order to get innovative, diversified, exhaustive and efficient solutions.
Keywords :
fission reactor coolants; fission reactor design; fission reactor instrumentation; fission reactor monitoring; fission reactor safety; liquid metal fast breeder reactors; nondestructive testing; nuclear engineering computing; nuclear reactor maintenance; ultrasonic transducers; AREVA; ASTRID sodium cooled fast reactor; CEA; EDF; ISI&R; R&D axes; acoustic surveillance; associated robotics; chemical transducer; coordinated research program; fission chamber development; generation IV sodium-cooled fast reactor; in-service inspection; inspection techniques; iterative method; laser repair intervention processes; measurement techniques; monitoring instrumentation; periodic inspection tool; pluriannual SFR research program; primary system conceptual design improvement; reactor design; reactor instrumentation; reactor repair; repair processes; robotic equipment; ultrasonic non destructive simulation; ultrasonic transducer; Detectors; Inductors; Inspection; Maintenance engineering; Monitoring; Temperature measurement; Temperature sensors; ASTRID prototype; In-Service Inspection & Repair; SFR; nuclear reactors; sodium;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2011 2nd International Conference on
Conference_Location :
Ghent
Print_ISBN :
978-1-4577-0925-8
Type :
conf
DOI :
10.1109/ANIMMA.2011.6172910
Filename :
6172910
Link To Document :
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