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Showing items 1-19 of 19

Alternating Thermal Loads in a Pipe Tee Caused by a Leaking Valve During Operation

Ackermann, R.; Holzer, W.; Kroiß, G. (IASMiRT, 1995-08-13)
Component Fatigue Life Evaluation Using Fragmentary Load Histories

Golembiewski, H.-J.; Tulke, K.; Marsch, S.; Baumann, F. (IASMiRT, 1995-08-13)
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. (IASMiRT, 1995-08-13)
Effect of Cu on Ferritic Steels Hardening under Irrdiation

Smetniansky-De Grande, N.; Barbu, A. (IASMiRT, 1995-08-13)
Fatigue Cracking on Reheater Waterooxes. Thermal And Mechanical Approach. Preventive Measures

Gauchet, J.P.; Faidy, C.; Journoud. P., Chhu; S.C., Berglas; E. (IASMiRT, 1995-08-13)
Improvement of the Final Disposal Behaviour of Burned Spherical Fuel Elements

Hurtado, AM.; Manderbach, Th.; Kolb. H.-A. (IASMiRT, 1995-08-13)
Internal Structure Vibratory Monitoring of 54 French PWRs

Trenty, A. (IASMiRT, 1995-08-13)
Life Assessment of Alloy 600 RPV Penetrations

Faidy, C.; Pichon, C. (IASMiRT, 1995-08-13)
Maintenance of Major Edf Components

Bacot, J. (IASMiRT, 1995-08-13)
Management of Component Integrity and Aging During Operation: The Effect on PWR-PLEX

Hienstoifer, W.G. (IASMiRT, 1995-08-13)
Radioactive Waste Disposal Plan in Korea

Seo, J.M.; Park, B.Y.; Hwang, T.W.; Choi, K.S.; Park, H.S. (IASMiRT, 1995-08-13)
Recent Technology Developments in Waste Management At Nuclear Facilities

Kohli, R. (IASMiRT, 1995-08-13)
Residual Life Determination and Qualification of Pressurizer Spray Lines

Blumer, U.R. (IASMiRT, 1995-08-13)
Seventeen Years of Transient Monitoring Experience in French PWR Units

Savoldelli, D. (IASMiRT, 1995-08-13)
Shaft Crack Detection on Centrifugal Pumps by Vibration Analysis

Serra, R.C.; Tecco, D.G. (IASMiRT, 1995-08-13)
Structural Mechanics Aspects of Nuclear Non-Reactor Facilities

Hadjian. A.H., Massie; H., Blackman (IASMiRT, 1995-08-13)
Substitution of Cobalt Alloying in PWR Primary Circuit Gate Valves

Cachon, L.; Sudreau, F.; Brunel, L.; Denape, J.; Lelait, L. (IASMiRT, 1995-08-13)
Thermal Embrittlement of Reactor Vessel Steels

Corwin, W.R.; Nanstad, R.K.; Alexander, D.J.; Odette, G.R.; Stoller, R.E.; Wang, J.A. (IASMiRT, 1995-08-13)
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. (IASMiRT, 1995-08-13)

Showing items 1-19 of 19