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17th International
Conference on |
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DIVISION D: AGING, LIFE EXTESION AND LICENSE RENEWAL
D01 - International Regulatory and Economics Perspectives
| D01-1 |
Assessment and Management of Aging of Nuclear
Power Plant Safety-Related Structures (D457) |
| D01-2 | The AMES network in the
6th Framework Programme (D267) F. Sevini, L.Debarberis, N.Taylor, R. Gerard, C. English, M. Brumovsky |
| D01-3 | Life Cycle Management
in the US Nuclear Power Industry (D545) George E. Sliter |
| D01-4 | Regulatory Strategy for
Operational Safety and Aging Management of NPPs in Korea (D555) H. J. Kim, H. K. Kim, T. E. Jin |
| D01-5 | Development of Periodic
Safety Review Technology in Korea (D034) Tae-Ryong Kim |
D02 - Utility Perspectives, WWER Technology
| D02-1 |
Safety Aspects of Long-term Operation of Nuclear
Power Plants (D524) |
| D02-2 | Lifetime-Management and
Operational Lifetime Extension at Paks Nuclear Power Plant (D112) T. Katona, A. Jánosiné Bíró, S. Rátkai, A. Tóth |
| D02-3 | Aging Assessment of CANDU
Plant Major Components for PLIM Feasibility Review (D535) Kyoung-Soo Lee, Il-Seok Jeong, and Tae-Ryong Kim |
| D02-4 | Material Properties Degradation
Assessment of the First Generation WWER-440 RPV after Prolonged Operation
(D182) Igor Gorynin, Boris.Timofeev, Tatiana Chernaenko |
| D02-5 | Surveillance Specimen
Programmes for WWER Reactor Vessels in the Czech Republic (D026) Jiri Brynda, Jozef Hogel, Milan Brumovsky |
| D02-6 | VVER-1000 Base Metal Reference
Steel and its Characterisation (D225) Luigi Debarberis, Beatriz Acosta, Soraia Pirfo, F. Sevini, A. Kryukov, F. Gillemot, A.Chernobaeva, M. Brumovsky |
D03 - Fatigue, Corrosion and Crack Issues
| D03-1 |
Study of Crack Propagation in a Multicracked Structure
in Thermal Fatigue (D210) |
| D03-2 | Fatigue Evaluation of
Dissimilar Welds on Nuclear Components (D080) Jong-Sung Kim, Se-Hwan Lee, Tae-Eun Jin |
| D03-3 | Crack Growth Behavior
of Irradiated Austenitic Stainless Steels in BWR Environments (D444) O. K. Chopra, E. E. Gruber, W. J. Shack, J. Muscara |
| D03-4 | Mechanism of Fatigue Crack
Initiation in Austenitic Stainless Steels in Light Water Reactor Environments
(D445) O. K. Chopra, W. J. Shack, J. Muscara |
| D03-5 | Structural Assessment
of a Corrosion-Degraded Reactor Pressure Vessel Head (D448) Paul T. Williams, B. Richard Bass |
| D03-6 | Condition Monitoring of
Flow-Accelerated Corrosion of a Simulated Low Alloy Steel Piping Elbow using
Electrochemical and Vibration Sensors (D320) Na Young Lee, Chi Bum Bahn, Si Hyoung Oh, Il Soon Hwang, Jung Taek Kim, Vincent K. Luk |
D04 - Component Integrity
| D04-1 |
Ageing Management of the Steam Generators of the
Nuclear Power Plant GKN (D530) |
| D04-2 | Life Cycle Management
of PWR Pressurizer (D539) Keshab K. Dwivedy, Nitin J. Shah, Mark A. Gray |
| D04-3 | Ageing Evaluation Model
of Nuclear Reactors Structural Elements (D313) Antanas Ziliukas, Audrius Jutas, Vitalis Leisis |
| D04-4 | Application of the Seebeck
effect for the Monitoring of the Neutron Embrittlement and Low-cycle fatigue
in Nuclear Reactor Technology (D585) M. Niffenegger, K. Reichlin, D. Kalkhof |
| D04-5 | Wear Behavior of Steam
Generator Tubes in Nuclear Power Plant Operating Condition (D045) In-Sup Kim, Jin-Ki Hong, Hyung-Nam Kim, Ki-Sang Jang |
| D04-6 | Experience Acquired from
the Equipment Qualification Process of the Temelin NPP (D521) Marek Tengler, Dr. Rudolf Masopust, Milan Vrána |
D05 - Aging Assessment and Monitoring
D06 - Containment and Others Structures
| D06-1 | Risk-Informed Assessment
of Degraded Containment Structures (D455) B. W. Spencer, D. M. Kunsman, H. L. Graves |
| D06-2 | Structural Analysis Research
Needs for Advanced Reactors (D456) Syed A. Ali, Herman L. Graves, III |
| D06-3 | Development of Integrated
Aging Management System for Containment Building (D252) Myung-Sug Cho, Young-Chul Song, Jong-Suk Lee, Sung-Wook Kim |
| D06-4 | Risk-based Replacement
Strategies for Redundant Deteriorating Reinforced Concrete Pipe Networks
(D546) Bryan Adey, Olivier Bernard, Bruno Gerard |