17th International Conference on 
Structural Mechanics in Reactor Technology


 

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)
D. J. Naus, H. L. Graves, III, B. R. Ellingwood

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)
Paolo Contri, Tamás Katona

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)
M. Seyedi, S. Taheri, F. Hild, J-M Stephan

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)
J. Bartonicek, W. Zaiss, F. Schöckle

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

D05-1

The TVO Pipeline Analysis and Monitoring System (D185)
Paul Smeekes, Aarne Lipponen, Heikki Raiko and Heli Talja

D05-2 Monitoring of Thermal Stresses in Steam Generators (D515)
Bohdan Weglowski, Jan Taler, Piotr Duda
D05-3 Application of DIALIFE system for Residual Life Time Assessment on Nuclear Power Plants (D406)
Dušan Vincour
D05-4 Application of Neural Networks for Finding the Relation between Stress and Operational Parameters of NPP Temelín (D536)
Leoš Ružek
D05-5 COMSY Software Assists Lifetime Management Activities (D187)
A. Zander, H. Nopper
D05-6 Inverse Method for Stress Monitoring in Pressure Components of Steam Generators (D489)
Piotr Duda
D05-7 Ageing Management - a New Key Word for Inaction? (D438)
Josef Jansky
D05-8 Process Data Reconciliation in Nuclear Power Plants (D435)
Magnus Langenstein, Josef Jansky
D05-9 MAFES, HUMOS and LEMOP Diagnostic Systems-Applications in NPP Temelin (D542)
Oldrich Matal, Oldrich Matal, jun., Josef Žaloudek
D05-10 Application and Importance of Ageing Management in Plant Life Extension Programme, Swiss NPP's (D054)
Reinhard Fuchs, Jan Stejskal, Daniel Steudler, Kurt Thoma
D05-11 Ageing Management Program of Safety Components: A Systematic Procedure (D567)
Claude Faidy

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


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