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Proceedings
International Association for Structural Mechanics in Reactor Technology (IASMiRT)
1991 - SMiRT 11 - Tokyo, Japan
Browsing 1991 - SMiRT 11 - Tokyo, Japan by Issue Date

Browsing 1991 - SMiRT 11 - Tokyo, Japan by Issue Date

Now showing items 1-20 of 623

Fatigue and Failure Behavior of a Mechanically Loaded Pipe Bend in High Temperature Water with Elevated Oxygen Content

K. Kussmaul; H. Diem; D. Uhlmann; H. Hunger; G. Katzenmeier (IASMiRT, 1991-08-18)
The Probabilistic Assessment of Steam Generator Leak Rate During a Secondary Side Accident

P. Hernalsteen (IASMiRT, 1991-08-18)
Practical Experience of Annealing to Extend WWER Reactor Vessels Lifetime

Y.G. Dragunov; V.G. Fedorov; A.V. Tetmanchuk; M.F. Rogov (IASMiRT, 1991-08-18)
Development of Energy Density Method for Inelastic Notch-Tip Strain Calculation and its Application for Pressure Vessel and Piping Design

A.V. Tashkinov; V.M. Filatov (IASMiRT, 1991-08-18)
Investigation of Materials from the Decommissioned Reactor Pressure Vessel of Gundremmingen Unit A Power Plant

K. Kussmaul; J. Fohl; T. Weissenberg (IASMiRT, 1991-08-18)
Influence of Axial Defects on Pressure Tube Integrity in Large Break Loca Analysis

P.S. Kundurpi; A.P. Muzumdar (IASMiRT, 1991-08-18)
Comparison of Reactor Pressure Vessel Codes with Respect to Brittle Fracture Assessment

M. Brumovsky (IASMiRT, 1991-08-18)
Factors That Affect Tube-Tubesheet Joint Integrity

P.W. Martin (IASMiRT, 1991-08-18)
Predicting Crack Arrert in Reactor Pressure Vessels

T.J. Griesbach; E. Smith (IASMiRT, 1991-08-18)
Fracture Behavior of A533B Class-1 Steel: Effects of Dynamic Strain-Aging and Neutron Irradiation

K.L. Murty; Y.H. Jung; S.T. Mahmood; D.S. Sarma (IASMiRT, 1991-08-18)
Structural and Fracture Mechanics Study of a Pipe with a Circumferential Crack Under Blowdown-Induced Loading

S. Brosi; R. Wanner; K. Reichlin; D. Schrammel; E. Kobes (IASMiRT, 1991-08-18)
Load Bearing Capacity of Degraded Pipe System When Subjected to a Blowdown-Induced Waterhammer

K. Kussmaul; H. Diem; E. Kobes; D.G. Schrammel; S. Brosi (IASMiRT, 1991-08-18)
Experiments on Crack Opening and Leak Rate Behavior of Small Piping Components at the HDR Facility

H.A. Hunger; G. Katzenmeier; H. Grebner (IASMiRT, 1991-08-18)
Comparisons of Irradiation-Induced Shifts in Fracture Toughness, Crack Arrest Toughness and Charpy Impact Energy in High-Copper Welds

W.R. Corwin; K.R. Nanstad; S.K. Iskaander (IASMiRT, 1991-08-18)
Analysis of the Conditions of Brittle Failure of WWER Type of Reactor Pressure Vessels on the Basis of Large Scale Specimen Testing

A.B. Getmanchuk; A.I. Fedosov (IASMiRT, 1991-08-18)
Non-Destructive Examination of Kinetic Sleeves

S.W. Glass; M. Tsunematsu; Y. Harada (IASMiRT, 1991-08-18)
Environmental Effects on the Crack Growth Properties of Alloy 600

N. Konda; K. Toyama; K. Tokimasa (IASMiRT, 1991-08-18)
Crack Analysis of Cladded Mockups in the Frame of Brittle and Ductile Fracture

D. Gilles; D. Moinereau (IASMiRT, 1991-08-18)
Mechanical Behavior of the HAZ in Reactor-Pressure-Vessel-weldments Before and After Irradiation

E.N. Klausnitzer; G. Hofmann; C. Leitz (IASMiRT, 1991-08-18)
Combination of Radiation and Hydrogen Damage of Reactor Pressure Vesel Steels

M. Ruscak; K. Splichal; A. Brozova; J. Zdarek (IASMiRT, 1991-08-18)

Now showing items 1-20 of 623