| F01 |
Stress
Assessment of a Component Using 3D Finite Element Models
Mattar Neto, M., Miranda, C.A.J., Cruz, J.R.B., Bezerra, L.M. |
| F02 |
ASME
Limits and Contradictions in the Finite Element Analysis of Pressure Vessels
Bezerra, L.M., Cruz, J.R.B, Miranda, C.A.J., Mattar Neto, M. |
| F03 |
A
Simplified Inelastic Analysis Method of Structures Applicated in the Case
of Large Variations of Temperature
Lejeail, Y., Gatt, J.M., Cabrillat, M.T. |
| F04 |
Experimental
Investigations Into Consequences of a Fuel Channel Failure in a CANDU Reactor
Kundurpi, P.S., Hadaller, G.I. |
| F05 |
Stress
Analysis of a Reinforced Horizontal Cylindrical Pressure Vessel Resting
on Saddles
Miranda, C.A.J., Aquino, C.T.E. |
| F06 |
Modified
Solution of Radial Nozzle With Thick Reinforcement in Spherical Vessel Head
Subjected to Radial Load
Lee, Y.-S., Sohn, Y.-S. |
| F07 |
Failure
of Pressurized Reactor Vessels Due to Severe Pressure Transients
Sirtori, S., Lo Conte, A., Miccoli, S. |
| F08 |
Evaluation
of the Overall Collapse of a Ring-Stiffened Cylindrical Shell
Mattar Neto, M., Miranda, C.A.J., Cruz, J.R.B., Silveira, R.C. |
| F09 |
Stress
Analysis of a Research PWR Pressure Vessel: A General Description
Miranda, C.A.J., Mattar Neto, M., Oliveira, C.A., Cruz, J.R.B., Bezerra,
L.M., Albuquerque, L.B., Assis, G.M.V. |
| F10 |
Stress
Analyses of the Intemals of a Research PWR Vessel: A General Overview
Miranda, CAJ., Mattar Neto ,M., Oliveira, C.A., Cruz, J.R.B.,
Bezerra, L.M., Assis, G.M.V., Albuquerque, L.B. |
| F11 |
PWR
Pressure Vessel Stress Analysis With Axisymmetric Model and Harmonic Loading
Albuquerque, L.B., Assis, G.M.V., Miranda, C.A.J., Cruz, J.R.B. |
| F12 |
Experimental
Validation of CASTEM Code for Buckling Problems
Damodaran, S.P., Chellapandi, P., Chetal, S.C., Bhoje, S.B. |
| F13 |
Integrity
Of The Blowdown Piping Systems in a Nuclear Power Plant - Findings And Consequences
Jansky, J., Langenstein, M. |
| F14 |
Stress
Analysis of Cylindrical Vessel Support Saddles
Albuquerque, L.B., Miranda, C.A.J. |
| F15 |
Evolution
of Generic Supporting Conditions for Feeders of 500 Mwe PHWR
Prasad,.K.H., Mishra, R., Soni, R.S., Gupta, K.N., Kushwaha, H.S., Bapat,
C.N., Mahajan, S.C., Sharma, V.K., Kakodkal, A. |
| F16 |
Modelling
Study of Sliding Interface Contact in Pipe Coupling
Chawla, D.S., Kushwaha, H.S., Mahajan, S.C. |
| F17 |
Piping
Elastic Calculations With a Method Allowing for Section Ovalization
Berton, M.N., Lejeail, Y., Cabrillat, M.T. |
| F18 |
Orthotropic
Elastic Beam-Type Formulation for Elbows
Berton, M.N., Lejeail, Y., Cabrillat, M.T. |
| F19 |
Evaluation
of Surge Line Thermal Stratification and Implementation To Piping Design
Yu, Y.J., Park, S.H., Sohn, G.H., Bak, W.J. |
| F20 |
A
Model for Plastic Hinges in Tubular Beam Impact
Sonzogni, V.E. |
| F21 |
Displacement
Estimates of Pipe Elbows Prior to Plastic Collapse Loads
Jospin, R.J. |
| F22 |
Piping
Seismic Design Criteria: Fatigue-Ratchetting Behaviour Under High Cyclic
Loadings
Touboul, F. |
| F23 |
Collapse
Characteristics of PHT Pump Discharge Elbow of an Indian PHWR
Bhattacharya, A., Kushwaha, H.S., Mahajan, S.C. |
| F24 |
An
Assessment of Proposed Changes in a ASME Section III Allowable Stresses
on the Critical Flaw Size Of Piping
Krishnaswamy, P., Ghadiali, N., Wilkowski, G. |
| F25 |
Piping
Seismic Design Criteria: Design of a Seismic Piping Test
Le Breton, F, Touboul, F., Blanchard, M.T. |
| F26 |
Further
Development of a Static Seismic Analysis Method for Piping Systems: The
Load Coefficient Method
Stevenson, J.D., Adams, T.M. |
| F27 |
Post-Calculation
of a Feed Water Pipe Break at the Loviisa Nuclear Power Plant
Saarenheimo, A., Eerikainen, L., Keskinen, R. |
| F28 |
Pipe
Bend Behaviour at Load Levels Beyond Design
Kussmaul, K., Diem, H.K., Uhlmann, D., Kobes, E. |
| F29 |
Creep
Tests on Ferritic Perforated Tubes
Cesari, F.G., Piolanti, P., Garzillo, A. |
| F30 |
Some
Numerical Results for Nonlinear Bending of Tubes
Selke, C.A.C., Luersen, M.A., Pereira, J.T., Lmaeda, F.T. |
| F31 |
3-D
Structural and Fatigue Analysis of Feeder Coupling Components
Chawla, D.S., Kushwaha, H.S., Mahajan, S.C. |
| F32 |
Fracture
Evaluation of a Crack in the Service Water Piping System to an Emergency
Diesel Generator
Rudland, D., Scott, P., Rahman, S., Wilkowski, G. |
| F33 |
C
(T) and Large Diameter Pipe Fracture Evaluations of a Fusion Line Crack
in a Bimetallic Weld
Scott, P., Francini, R., Rahman, S., Rosenfield, A., Wilkowski, G. |
| F34 |
Simulation
of a Stainless Steel Multipass Weldment
Lejeail, Y., Cabrillat. M.T. |
| F35 |
One
Example of Modelization of Residual Stresses in Nuclear Power Plants: The
Bimetallic Junction
Frelat, J., Taheri, S., Todeschini, P. |
| F36 |
A
Study on Residual Stress of Butt-Welded Plate Joint Using Inherent Strain
Analysis
Mochizuki, M., Saito, N., Enomoto. K., Sakata, S., Saito, H. |
| F37 |
On
a New Method of Residual Stress Field Measurements
Lejeail, Y., Cabrillat, M. T. |
| F38 |
Structural
Analisys of Non-Uniformly Perforated Plates
Malekian, C., Detroux, P., Petit, A., Papageorges, A. |
| F39 |
Fatigue
Analisys of Recuperative Heat Exchanger
Costa Filho, P.A., Suanno, R.L.M, Ferrari, L.D.B. |
| F40 |
The
Effect of Mechanical Characteristics of Steels on the Residual Stress Level
After Pressing in of Heat Exchanging Tubes in Steam Generator Collectors
Stepanov, G.V., Kharchenko, V.V., Shatko, A.A., Dranchenko, V.V., Titov,
V.F. |
| F41 |
Limit
Collapse Load Analysis of Perforated Plates
Bhasin, V., Kushwaha, H.S., Mahajan, S.C. |
| F42 |
Analytical
and Experimental Studies of Mechanical Consequences of a Steam Generator
Tube
Duc, B., Sudreau, F., Flesch, B., Rassineux, B. |
| F43 |
Highlights
Of The Fifth Symposium (SCI-NPP-SEP 5)
Gupta, A.K., Hassan, T. |
| F44 |
Off-Line System for Determination
of the Residual Life of Vessels By Experts
Vejvoda, S., Vincout, D.
|
| F45 |
Role
of Barc Parallel Processing System in Structural Analysis of Nuclear Components
Prasad, P.S., Dutta, B.K., Kushwaha, H.S., Mahajan, S.C., Kakodkar, A.
|
| F46 |
Analysis
of Sagging Behaviour Of PHWR Coolant Channel Following Postulated - Severe
Accident
Dutta, B.K., Kushwaha, H.S., Mahajan, S.C., Kakodkat, A. |
| F47 |
Overview
of the IPIRG-2 Program - Seimic Loaded Cracked Pipe System Experiments
Hopper, A., Olson, R., Scott. P, Wilkowski, G. |
| F48 |
A
Vibration Model for the Primary Circuit Of VVER-440 Type Reactors Based
on Finite Elements
Altstadt, E., Schefflet; M.. Weiss, F-P. |
| F49 |
Reduction
of Operational Vibration and Seismic Design of the Feed-Water Piping System
of the VVER-440/213 at PAKS
Katona, T., Ratkai, S., Delinic, K., Zeitnet, W. |
