General Articles
Vol.1 No.4 GA10
Copyright Journal compliation © 2010-2011 the Japan Society of Maintenology
Fig.1 History of Japan’s PWR
Fig.2 Past Achievements and Future Prospects for Ageing-related Research Activities
Fig.3 Industrial Efforts to Promote PLM-related R&D Activities
Fig.4 The History of PLM/AM at Japanese NPPs
Fig.5 Replacement of Major Components at Mihama#3
Fig.6 Inspection of Steam turbines
Fig.7 Schematic drawing of new low pressure turbines
Fig. 8 Case of deterioration : Baffle former bolts
Fig.9 Technical evaluation : Degradation modes of Core Internal (PWR)
Fig.10 Technical Evaluation of IASCC for Ohi#1(1/2)
Fig.11 Technical Evaluation of IASCC for Ohi# (2/2)
Fig.12 Integrity Evaluation of BFB - Multiple Ageing Phenomena -
Fig.13 Main Components Using Alloy 600 in J-PWR
Fig.14 The History of Trouble and PM of RV-Head
Fig.15 Case of deterioration : RV-haed penetration (1)
Fig.16 Case of deterioration : RV-head penetration (2)
Fig.17 Discovery of Cracking
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Fig.21 Non-Destructive Testing Technique - Stream Generator Nozzle Safe End Weld
Fig.22
Fig.23 Alloy 690(52) cladding for Reactor Vessel nozzle safe-end
Fig.24
Fig.25 Application of Lessons Learned from Past Events/Failures
Fig.26 Results of Ageing Management Study and Total Management System
Fig.27 Preparedness for the maintenance activities (viewpoint of information)
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