12th International
Conference on
Structural Mechanics
in Reactor Technology
|
12th International
Conference on |
|
DIVISION D: PERFORMANCE AND
LIFE CYCLE MANAGEMENT OF OPERATING REACTORS
(The papers with links are those
received by the SMiRT 12 Secretariat at the time the Transactions went to press)
D01: Component Aging
| D01/1 |
On Aging Factors,
Aging Mechanisms and Their Combinations in the Primary Circuit of NPP'S |
| D01/2 | Overview
of Research on Nuclear Plant Cable Aging and Life Extension Sliter, G.E. |
| D01/3 | Rule
Based Deterioration Identification and Management System Kataoka, S., Pavinich, W., Lapides, M.. |
| D01/4 | Nuclear
Power Plant Common Aging Terminology Sliter, G.E. |
| D01/5 | Reactor
Pressure Vessel Life Cycle Management at the Calvert Cliffs Nuclear Power
Plant Doroshuk, B.W., Bowman, M.E., Henry, S.A., Pavinich, W.A., Lapides, M.E. |
D02: International Perspective on Extended Operation
| D02/1 |
Overview of Plant Life Extension
Technology Development in Japan |
| D02/2 | Main
Problems and Directions of Activities on Life Extension of the Russian NPP's Bougaenko, S.E., Getman, A.F.. |
| D02/3 | Overview
of NPP's Component Aging Assessment Research Program in Taiwan Lai, H.-C., Wang, L.-H. |
| D02/4 | Periodic
Reviews of Structural Integrity Banks, P.J., Stokoe, T.Y., Thomas, D.L. |
| D02/5 | Angra-I
Operational Incidents - Ten Years of Evaluation Alvarenga, M.A.B., Barcellos, R.A., Costa, E.M., Soares, H.V., De Lima, J.M. |
| D02/6 | Plant
Lifetime Management and Resarch Program Sakai, K., Nagayama, M. |
D04: Fatigue Monitoring (1)
| D04/1 |
Monitoring
Systems and Procedure for Life Time Prediction of Components |
| D04/2 | Determination
of Actual Fatigue Usage of the Surge-Line In GKN 2 on the Basis of On-Line
Monitoring Schoeckle, F., Bartonicek, J., Kockelmann, H. |
| D04/3 | Trend
of Operating Data Monitoring and Fatigue Evaluation Systems for BWR in Japan
Takahashim, Y., Igi, K.., Maekawa, O., Tani, M. |
| D04/4 | Assessment
of Design Margin Fatigue of RPV Based on Operating Data Maekawa, O., Kanazawa, Y., Tsuneoka, O., Takahashi, Y., Kuribayashi, T., Hayashi, M., Matsumoto, K. |
| D04/5 | On-Line
Fatigue Monitoring and Margins Probabilistic Assessment Fournier, I., Morilhat, P. |
D05: Fatigue Monitoring (2)
| D05/1 |
New Developments
in French Transient Monitoring System: SYSFAC |
| D05/2 | Experiences
with the TÜV Pipe Monitoring System in the Grohnde Nuclear Power Station Dittmar, H., Hofstöetter, P. |
| D05/3 | Development
of Methodology for On-Line Fatigue Life Monitoring of Nuclear Power Plant
Components Mukhopadhyay, N.K., Dutta, B.K., Kushwaha, H.S. |
| D05/4 | Operational
Monitoring of the Long-Tme Characteristics of Components - Computing Algoithms
for Determining the Current Degree of Fatigue Hüettner, Ch., Kroiss, G. |
| D05/5 | Component
Fatigue Rates Drawn from Measured Load Histories - Case Study of a PWR Surge
Line Using FAMOS Golembiewski, H.-J., Tulke, K. |
D08: Valves
| D08/1 | Valve Packing Study Cepkauskas, M.M., Garcia, C.M. |
| D08/2 | Checking
of Spring Loaded Safety Valves in German Nuclear Power Plants Beckendorf, H., Kalk, A., Pache, W., Kuckartz, B. |
| D08/3 | Thermal
Fatigue in Nuclear Valves: Three Dimensional Calculation of a Check Valve
Submitted to a Thermal Shock Chas, G., Masson, J.C., Moinereau, D., Scliffet, L. |
| D08/4 | Component
Spectral Identification and Seismic Analysis Application Panet, M., Morel, M. |
D10: Piping - Thermal Stratification
| D10/1 | Stress
Analysis of a 900 MWe Pressurizer Surge Line Including Stratification Effects Ensel, C., Colas, A., Barthez, M. |
| D10/2 | Inverse
and Direct Transfer Functions for the Fatigue Follow-up of Piping Systems
Submitted to Stratification Guyette, M., De Smet, M. |
| D10/3 | Experimental Investigation
of Thermal Striping in Steam Generator Feedwater Line Brunel, L., Morilhat, P., Fritz, R. |
| D10/4 | Laboratory
Tests of Stratified Flow in Horizontal Piping Jud, E., Crua, A., Blumer, U.R. |
D11: Cracking in BWR Water Environments
| D11/1 | Fatigue
Crack Growth Behavior in Weld Heat Affected Zone of Type 304 Stainless Steel
in High Temperature Water Itatani, M., Fukakura, J., Asano, M., Kikuchi, M., Chujo, N. |
| D11/2 | IGSCC
Susceptibility of Stainless Steel and Ni Base Allow in Simulated BWR Environment Saito, N., Kikuchi, E., Nakayama, G., Yamauchi, K., Suzuki, S. |
| D11/3 | IGSCC
Growth Rate of Sensitized Type 304 Stainless Steel in
Simulated BWR Environment Kikuchi, E., Itow, M., Sakamoto, H., Kuniya, J., Kitamura, M. |
| D11/4 | X18H10T Stainless
Steel Interaction with High-Temperature
Water in Presence of Zirconium Alloy in the Reactor System Petrosian, V. |
D12:
Miscellaneous Components and Degradation Mechanics
| D12/1 | BMI Thimble Wear Bellet, S., Ayme, S. |
| D12/2 | Defect
Analysis of Recirculation Pump Shaft Cracking Blumer, U.R., Frei, A. |
| D12/3 | Behavior of Internals
Baffle Assembly Bolts Bellet, S., Morel, A., Hedin, F., De Keroulas, F. |
| D12/4 | Fatigue
Cracks on Junctions Between Water Box and Tube Plate Feedheaters: Thermal
and Mechanical Approach-Remedial Action Gauchet, J.-P., Journoud, P.. |
| D12/5 | Development of a Repair
Technique for RPV Closure System Dworaczek, J.P., Jacquot, P., Kopacki, J.L., Rieg, C. |
| D12/6 | The
Study of Thermal Fatigue Problem on Reactor Recirculation Pump of BWR Plant Watanabe, A., Takahashi, Y., Igi, T., Miyano, T., Narabayashi, T., Iikura, T., Sagawa, W., Hayashi, M., Endo, A., Kato, H., Kanno, H., Hosokawa, M. |
DF09: Piping and
Piping Components
| DF09/1 | Alternative
Methods for PWR Primary Piping Analysis Induced by Operating Experience Pellissier-Tanon A., Grandemange, J.M., Heliot, J., Faidy, C., Proix, J.M. |
| DF09/2 | Evaluation of Carbon
Steel Piping in Applying Ice Plugging Procedure Ishiwata, M., Tayama, O., Takeda, S., Murabe, R., Iwata, K., Togasaki, M. |
| DF09/3 | Recirculation
Pumps & Core Pump & Piping Vibration Monitoring System Bognatz, S., Lefter, J., Tsacoyeanes, J. |
| DF09/4 | Diagnosis of Main Steam
Line Vibration Problems For the Point Lepreau Nuclear Generating Station Lin, C.-W., Anderson, P., Loey, H., Blomsma, B., Murphy, R., Boudreau, G. |
| DF09/5 | Fluid
and Structural-Dynamic Piping Analysis Korthauer, H. J., Lange, H., Rychlik, G. |
DG03: Annealing (1)
| DG03/1 | AMES/IAEA WG NPLM Davies, M. |
| DG03/2 | Steel Embrittlement/AMES Matthews, J., English, C. |
| DG03/3 | Pressure
Vessel Annealing for Plant Life Management (PLM): Tensile and Hardness Properties
and Irradiated, Annealed and Re-Irradiated Low Alloy Steel Tipping, P.G., Cripps, R.C. |
| DG03/4 | Superheated
Steam Annealing of Pressurized Water Reactor Vessel Porowski, J.S. |
| DG03/5 | Recent
Evaluation of "Wet" Thermal Annealing to Resolve Reactor Pressure
Vessel Embrittlement Server, W.L., Biemiller, E.C. |
DG07: Steam Generator
Experience
| DG07/1 | How
to Operate Safely Steam Generators with Multiple Tube Through-Wall Defects Hernalsteen, P. |
| DG07/2 | Propagation
of Stress Corrosion Cracks in Steam Generator Tubes Cizelj, L., Mavko, B., Riesch-Oppermann, H., Brüeckner-Foit, A. |
| DG07/3 | Stress
Identification in Steam Generator Tubes from Profile Measurements Andrieux, S., Voldoire, F. |
| DG07/4 | Experimental Determination
of Operating Stresses in the Transition Zone of 900 MWE PWR Steam Generator
Tubes Brunet, J.P., Riou, J.C., Flesch, B., Granger, B., Chabrerie, J. |
| DG07/5 | Steam Generator Design
Features for Power Uprating Achievements Bouecke, R. |
DG13: Annealing (2)
| DG13/1 | Test Method
and Equipment for the Fracture Toughness Evaluation for Pressure Vessel
Materials Using Small-Size Specimens Lebedev, A.A, Chausov, N.G., Getmanchuk, A.B. |
| DG13/2 | Fracture Mechanics Evaluations
to Assure Structural Integrity of Operating Plant Components Subject to
Toughness Degradation by Irradiation and Aging Mehta, H.S. |
| DG13/3 | A Promising Method for
Enhancing Brittle Fracture Resistance of Pressure Vessels V.Y. Dragunov, Y.G. |
DH06: Concrete and
Containment Structures
| DH06/1 | Aging
Management for Safety Related Concrete Structures in Switzerland Zwicky, P.F., Kluge, D. |
| DH06/2 | Remnant
Life Preservation of LWR Plant Structures Gregor, F.E., Hookham, C. J. |
| DH06/3 | A
Data Base for Aging of Structural Materials Oland, C.B., Naus, D.J., Jerath, S. |
| DH06/4 | A
Study of the Life Expectancy of Cooling Towers Bolvin, M., Chauvel, D. |
| DH06/5 | Continuing
the Service of Aging Concrete Structures in Nuclear Power Plants Naus, D., Oland, C.B., Arndt, E.G. |