12th International
Conference on
Structural Mechanics
in Reactor Technology
|
12th International
Conference on |
|
DIVISION F: PRESSURE COMPONENTS,
DESIGN TECHNOLOGIES, AND RESEARCH FOR REGULATORY NEEDS
(The papers with links are those received
by the SMiRT 12 Secretariat at the time the Transactions went to presss)
F01: Component Testing and Analysis: Vessel
| F01/1 |
Computations of
Principal Stresses and Stress Intensity of a Nozzle on a Spherical Pressure
Vessel |
| F01/2 | Stress Analyses
of a Prestressed Cast Iron Reactor Pressure Vessel for Modular High Temperature
Reactors Geiss, M. |
| F01/3 | Strain Assessment
in 2-D Problems of Elasto-Plastic Bending with Tension of Pressure Vessel
Walls Tashkinov, A.V., Filatov, V.M. |
| F01/4 | Large
Deflection Analysis of Strength and Stability of a Corrugated Thin-Walled
Vacuum Chamber Skrzypek, J., Skoczen, B. |
| F01/5 | Theoretical
and Experimental Investigations of Instability of Thin-Walled, Corrugated
Tubes Kurtyka, T., Brunet, J.-C., Skoczen, B. |
| F01/6 | The
Calculations of the Stress-Strain State of Graphite Bricks of the Uranium-Graphite
Reactors and the Prognosis of the Destruction of the Graphite Stack RBMK-Reactors Manevski, V.N., Platonov, P.A., Chugonov, O.K., Alekseev, V.M., Karpukhin, V.I. |
F02: Component Testing and Analysis: Piping and Piping Components
| F02/1 |
Elbow Curve Subjected to Bending Moment on the
Plane |
| F02/2 | Experimental
and Theoretical Investigation of Stresses and Flexibility Coefficients at
Pipe Junctions Gowda, S.P.T.R., Paramasivam, V., Achyutha, H., Udayasurian, K., Kadiravan, C., Kakodkara, A., Kushwaha, H.S. |
| F02/3 | Response of Piping Using
Three Different Types of Support Under Shock Loading Maneschy, J.E., Lopes, V. |
| F02/4 | Evaluation
of Primary Stress Indices for Mitre Bends and Possibility of Extending to
Do/T ›
50 Murali, B., Munshi, D., Vaze, K.K., Kushwaha, H.S. |
F03: Component Testing and Analysis: Welding
| F03/1 |
Design Improvement
of Weld Design of Rip Motor Casing to RPV Nozzle |
| F03/2 | Welding
Residual Stress Analysis and Measurement in Repaired Weldment Wang, L.H., Lin, S.W., Lin, M.W., Yen, H.Y. |
| F03/3 | Measurement
of Residual Stresses in Weld Overlay of Pipe Component Yen, H.J., Chen, L.J., Lin, M.C.C. |
| F03/4 | Development
of Micro Machining Tools for Finishing Weld Joint Motoyama, M., Tamai, Y., Takahashi, Y., Akasaka, M., Yamada, Y., Hamamoto, Y. |
| F03/5 | Elasto-Plastic
Strain Investigation at Notch Tips in Non-Uniform Nominal Stress Field Tashkinov, A.V., Filatov, V.M., Krenevicius, A., Suksta, M. |
F04: Tube Sheet and Perforated Plate: Design
| F04/1 |
Effective
Elastic Method for Perforated Plates with Irregular Penetration Patterns |
| F04/2 | Determination
of the Equivalent Properties of Perforated Plate by Numerical Experiment Bhattacharya, A., Buragohain, D.N., Kakodkar, A. |
| F04/3 | Non
Linear Analysis of Perforated Circular Plates with Square Penetration Patterns Targowski, R., Lamblin, D., Guerlement, G. |
| F04/4 | A
Study on the Load Distribution Factor in the Perforated Square Plate with
Elastic Support Lee, Y.S., Yim, J.S. |
F05: Design Codes and Structural Analysis
| F05/1 | Nuclear
Piping Design - An Overview Pattabiraman, J., Neelwarne, A. |
| F05/2 | Development and Improvement
of Regulating Documents on Strength Assurance in Reactor Technology Bougaenko, S.E., Makhutov, N.A. |
| F05/3 | Structural
Evaluation of Containment Design of the SBWR Plant for Severe Accident Conditions Sawhney, P.S., Kadari, I., Duchon, N.B., Liu, A., Gou, P.F. |
| F05/4 | Selection
of Elements for Stress Analysis of Reactor Containment Bhattacharya, A., Kushwaha, H.S., Mahajan, S.C. |
F06: Piping and Piping Components (1)
| F06/1 | Experimental
Investigations on the Strength and Fracture Behavior of Degraded Piping
Components Schwartz, Th., Herter, K.-H., Julisch, P., Stoppler, W. |
| F06/2 | Failure
of Expansion Joint Tie Rods - Impact on Bellows Integrity Daugherty, W.L., Miller, R.F. |
| F06/3 | Methodology for Optimisation
of Design of Coolant Channel Spacer Sinha, S.K., Sinha, R.K. |
| F06/4 | A Methodology for Determining
Operability Margins in Motor-Operated Gate Valves Steele, Jr. R., Dewall, K.G., Watkins, J.C. |
| F06/5 | Calculation
of Crack Opening and Leak Rate of Piping Components with Comparison to Experiments
at the HDR-Facility Grebner, H., Hunger, H., Höefler, A. |
| F06/6 | Results
of a Leak Rate Bench Mark Test on the Basis of Experiments at the HDR-Facility Grebner, H. |
F07: Piping and Piping Components (2)
| F07/1 | Spring
Effects and Primary Stress Roche, R.L. |
| F07/2 | Local Postweld Heat
Treatment for Weld Joint in Reactor Pressure Vessel Nozzle/Safe-End By Induction
Heating Hirano, T., Okamoto, A., Yoshida, K., Matsushita, A. |
| F07/3 | In-Containment
Noise Identification and Resolution of an Operating Nuclear Power Plant Chang, K.C., Patel, R.B., Flannigan, R.D. |
| F07/4 | Experimental
Development of Rolled Joints for ZR-2.5 WT% NB Pressure Tubes for Use in
Indian PHWRS Madhusoodanan, K., Sinha, R.K. |
| F07/5 | Study on Mechanical
Properties of Carbon Steel Pipe Material After Exposure to Cryogenic Coolants Togasaki, M., Sakamoto, H, Hirata, H., Murabe, Y., Hosoya, K., Sasaki, T. |
F08: Steam Generators
| F08/1 | Tightness
of Steam Generator Bolt Joints in Actual Service Conditions Vejvoda, S. |
| F08/2 | Analytical and Experimental
Studies of Mechanical Consequences of a Steam Generator Tube Rupture Flesch, B., Duc, B. |
| F08/3 | Assessment of Steam
Generator Tube Integrity Splichal, K., Brozova, A., Karnik, D., Zdarek, J. |
F09: Reactor Vessel Irradation and Surveillance
| F09/1 | Preliminary
Irradiation Test Results from the Yankee Atomic Electric Company Reactor
Vessel Test Irradiation Program Biemiller, E.C., Fyfitch, S., Campbell, C.A. |
| F09/2 | Strucural
Features and In-Service Inspection of LTHR-200 Pressure Vessel Dunshi, X., Shuyan, H., Junjie, L., Suyuan, Y. |
| F09/3 | Role
of Friction and Source Hardening in DSA and Radiation Embrittlement of Ferritic
Steels and Iron Murty, K.L., Hong, J., Zou, Y., Britt, J.C.. |
| F09/4 | A
Reactor Pressure Vessel Monitoring System for BWR Plants Kuo, A.Y., Chen, K.L.,Tang, Y.K. |
| F09/5 | The Reasonable Design
of Precracked Chappy-Size Specimen in Fracture Toughness Surveillance Test
of Nuclear Pressure Vessel Zhang, X.P., Shi, Y.W. |
F10: In-Service Inducted Degradations
| F10/1 | Operation with Cracked
Generator Rotor Jansky, J., Lazzeri, L. |
| F10/2 | Determination
of the Evolution in the Shape of Stress-Corrosion-Cracks in Some Typical
CRDM-Tubes Bhandari, S., Thomas, J.P. |
| F10/3 | Stress
Corrosion Cracking in Hotwater and Feedwater Vessels - Findings and Consequences
for Operation and Design Jansky, J., Langenstein, M. |
| F10/4 | Experimental
Investigation of a Flawed Pipe System Loaded with Temperature Stratification
and Pressure Hunger, H. |
| F10/5 | Fracture
Mechanics Analyses of a Longitudinally Cracked Bend Under Cyclic Loading Kussmaul, K., Uhlmann, D., Koski, K., Hunger, H. |
F11:
Structural Integrity Assessment (1)
| F11/1 | Comparing
Calculated and Experimentally Determined Failure Pressure of Pipes with
Longitudinal Surface Flaws Stoppler, W., Strum, D., De Boer, A. |
| F11/2 | Integrity
of Neighbouring Coolant Channels in the Event of a Single Coolant Channel
Failure in a PHWR Singh, R.K., Kushwaha, H.S., Mahajan, S.C., Kakodkar, A. |
| F11/3 | The
Failure Root Cause Analysis of Recirculating Sensing Line In Taiwan Chinshan
Nuclear Power Plant Ting, K. |
| F11/4 | Design
by Analysis of SBWR Key Components Micheli, I., Orsini, M. |
| F11/5 | Feedwater
Pipng Guillotine Breaks at 340°C Operation Temperature Jansky, J., Andrä, T., Albrecht, K. |
F12:
Structural Integrity Assessment (2)
| F12/1 | New Development of Reliability-Based
Structural Design Code for Korean Nuclear Power Plants Kim, S.H. |
| F12/2 | Structural Evaluation
of a BWR Containment Subject to Local Wall Thinning Due to Corrosion Mehta, H.S. |
| F12/3 | Improvements
in Thermal and Vibration Response of Moderator Heat Exchangers at Madras
Atmoic Power Station Rao, M.R.K., Murthy, L.G.K. |
| F12/4 | Stress Analysis of Composite
Structure of Revolution Youmei, P. |
| F12/5 | Optimum
Truss Design by Stochastic Simulated Annealing Lee, Ch.D., Lee, W.D. |
FG13: Thermal Stress and Fatigue (1)
| FG13/1 | Thermal-Elastic
Stress Analysis and Sealing Behavior of LTHR-200 Pressure Vessel Suyuan, Y., Suyuan, H., Junjie, L., Dunshi, X. |
| FG13/2 | Study
on Cylindrical Test Subjected to Oligocyclic Thermal Fatigue Cesari, F.G., Battistella, P., Quaranta, S., Arduino, M. |
| FG13/3 | Thermal
Analyses of INWA-Experiments for Modular HTR-Reactors Kneer, A., Häfner, W., Hejzlar, P., Schulz, R., Wolf, L. |
| FG13/4 | Behaviour
of a Pressure Vessel Nozzle with Thermo-Sleeve Under Thermal Loading Induced
by Stratified Flow Kussmaul, K., Mayinger, W., Diem, H., Katzenmeier, G. |
FG14: Thermal Stress and Fatigue (2)
| FG14/1 | Normative
Issues in Thermal Fatigue Merola, M. |
| FG14/2 | Prediction
of Crack Propagation in Type 304 Stainless Steel Cylindrical Specimens Subjected
to Cyclic Thermal Loads Fujioka, T., Takahashi, Y., Satoh, Y., Fukuda, Y. |
| FG14/3 | Fatigue
Evaluation of Piping Connections Under Thermal Transients De Aquino, C.T.E., Maneschy, J.E. |
| FG14/4 | Fatigue
Crack Growth Behaviour of Zr-2.5% Nb in a Candu Reactor Water Enviornment Lepik, O.E., McCluskey, D.M. |
FG15: Creep and Creep Fatigue (1)
| FG15/1 | Defect
Assessment Procedure: A French Approach for Fast Breeder Reactors Drubay, B., Moulin, D., Faidy, C., Poette, C., Bhandari, S. |
| FG15/2 | Creep
Fatigue Crack Initiation and Growth on Thick Circumferentially Notched 316
L Tubes Under Cyclic Thermal Shocks and Uniform Tension Poette, C., Albaladejo, S. |
| FG15/3 | Initiation
of Crack Under Creep and Creep-Fatigue Condition Drubay, B., Laiarinandrasana, L., Faidy, C. |
| FG15/4 | Analysis
of Non-Steady Asymptotic Crack Tip Fields in Power Law Creeping Materials Linkens, D., Dean, D.W., Busso, E.P. |
| FG15/5 | Fracture
Mechanics in Creep Situation: Interpretation of Results on a Test Specimen Deschanels, H., Turbat |
FG16: Creep and Creep Fatigue (2)
| FG16/1 | Creep Cracking in Pressurized
Tube at High Temperature Kiruchi, K., Muto, Y. |
| FG16/2 | Evaluation
of Surface Crack Propagation at Elevated Temperature Takahashi, H., Yoshizawa, H., Uno, T. |
| FG16/3 | Evaluation
of the Creep-Fatigue Behavior of Austenitic Stainless Steels Breitling, H., Staerk, E., Livesey, V.B., Mottot, M., Tavassoli, A.A. |
| FG16/4 | Crack
Growth Determination on Laboratory Components Hurst, R.C. |