13th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION D: LIFE CYCLE AND MANAGEMENT OF NUCLEAR INSTALATIONS AND WASTE TECHNOLOGY


D01 Structural Mechanics Aspects of Nuclear Non-Reactor Facilities
Hadjian. A.H., Massie, H., Blackman
D02 Maintenance of Major Edf Components
Bacot, J.
D03 EDF Feedback Shot-Peening On Feedwater Plants Working To 360°C - Prediction Correlation and Follow-Up of Thermal Stresses Relaxation
Gauchet, J.P., Barrallier, L., Leguernic, Y.
D04 Fatigue Cracking on Reheater Waterooxes. Thermal And Mechanical Approach. Preventive Measures
Gauchet, J.P., Faidy, C., Journoud. P., Chhu, S.C., Berglas, E.
D05 Substitution of Cobalt Alloying in PWR Primary Circuit Gate Valves
Cachon, L., Sudreau, F., Brunel, L., Denape, J., Lelait, L.
D06 Recent Technology Developments in Waste Management At Nuclear Facilities
Kohli, R.
D07 Radioactive Waste Disposal Plan in Korea
Seo, J.M., Park, B.Y., Hwang, T.W., Choi, K.S., Park, H.S.
D08 Thermo-Mechanical FE-Analysis of the Fabrication of a Cu-Fe Canister for Spent Nuclear Fuel
Josefson, B.L., Lindgren, L.-E., Haggbla,. H.-A,. Karlsson, L.
D09 Improvement of the Final Disposal Behaviour of Burned Spherical Fuel Elements
Hurtado, AM., Manderbach, Th., Kolb. H.-A.
D010 Seventeen Years of Transient Monitoring Experience in French PWR Units
Savoldelli, D.
D011 Management of Component Integrity and Aging During Operation: The Effect on PWR-PLEX
Hienstoifer, W.G.
D012 Internal Structure Vibratory Monitoring of 54 French PWRs
Trenty, A.
D013 Shaft Crack Detection on Centrifugal Pumps by Vibration Analysis
Serra, R.C., Tecco, D.G.
D014 Life Assessment of Alloy 600 RPV Penetrations
Faidy, C., Pichon, C.
D015 Residual Life Determination and Qualification of Pressurizer Spray Lines
Blumer, U.R.
D016 Alternating Thermal Loads in a Pipe Tee Caused by a Leaking Valve During Operation
Ackermann, R., Holzer, W., Kroiß, G.
D017 Component Fatigue Life Evaluation Using Fragmentary Load Histories
Golembiewski, H.-J., Tulke, K., Marsch, S., Baumann, F.
D018 Thermal Embrittlement of Reactor Vessel Steels
Corwin, W.R., Nanstad, R.K., Alexander, D.J., Odette, G.R., Stoller, R.E., Wang, J.A.
D019 Effect of Cu on Ferritic Steels Hardening under Irrdiation
Smetniansky-De Grande, N., Barbu, A.


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