18th
International Conference on
Structural Mechanics
in Reactor Technology
| 18th
International Conference on |
|
DIVISION
D: AGING, LIFE EXTENSION, AND
LICENSE RENEWAL
International
Experiences Related to Lifetime Extension I
| D01-2 | Methodology
on Ageing Management Review for Main Components of a PWR NPP Yikang Dou, Yinbiao He, Xuelian Xu, Ming Zhang, Xingyun Liang |
| D01-3 | Using
Lessons Learned to Improve the NPP License Renewal Process Jerry Dozier, Amy Hull, Steven West, Pao Tsin Kuo |
| D01-4 | Proof
of Integrity and Ageing Management of Mechanical Components in Nuclear Power Plants Eberhard Roos, Karl-Heinz Herter, Hans Kockelmann, Xaver Schuler |
| D01-5 | Integrity
Assessment Technology for the Aging Management Tae-Eun Jin |
| D01-6 | French
Nuclear Plant Life Management Strategy Application on Reactor Pressure Vessels
and Steam Generators Life Management Georges Bezdikian |
International
Experiences Related to Lifetime Extension II
| D02-4 | Key
Elements of the Ageing Management of the WWER-440/213 Type Nuclear Power Plants Tamás János Katona, Ágnes Jánosiné Bíró, Sándor Rátkai, Zoltán Ferenczi |
| D02-5 | Control
of Selected VVER Components Life Time SKODA JS a.s. Experience Jan Zdebor, Eugen Pribulla |
| D02-6 | Sampling
of Reactor Pressure Vessel Inner Cladding for Retrospective Dosimetry Analysis Miloslav Ruchar, Josef Hógel |
| D02-7 | Application
of System Dialife for Residual Life Time Assessment on Nuclear Power Plant Components Dusan Vincour, Ladislav Jurasek |
International Experiences Related to Lifetime Extension III
| D03-1 | Integrated
Plant Life Management (PLiM) - The IAEA Contribution Ki-Sig Kang, Claude Russell Clark, Akira Omoto |
| D03-3 | Ageing
Management of Nuclear Components: A Safety and Economical Issue Claude Faidy |
| D03-5 | Ageing
Management Database Development for PWR NPP Steam Generator Hongyun Liu, Liangjun Xu, Changhuai Xiong, Xianyuan Wang |
| D03-8 | Piping
Vibration Stress Measurement and Life Assessment Nianwen Lu, Xiaolong Wang, Xiaozhen Wu |
Fatigue Issues
| D04-1 | High
Cycle Thermal Crazing: a Phenomena Related to the Structure Said Taheri, Erwan Galenne |
| D04-2 | Evaluation
of Environmental Fatigue Lifetime for Nuclear Welded Structure Based on Structural
Stress and Fracture Mechanics Approach Jong-Sung Kim, Tae-Eun Jin |
| D04-4 | Comparison
between S-N-P Curves Obtained from Constant Stress and Step-Stress Fatigue Tests
João Mário Andrade Pinto, Tanius Rodrigues Mansur, Miguel Mattar Neto, Enrico Antonio Colosimo |
| D04-5 | Thermal
Fatigue of Reactor Components in OECD-NEA Member Countries: a Three Fold Program
to Enhance Cooperation Claude Faidy, Stéphane Chapuliot, E. Mathet |
| D04-6 | An
Approach for Low Cycle Fatigue Life Prediction of Various Metallic Materials Subjected
to Non-Proportional Multiaxial Loading Haisheng Yu, S.N. Shukayev |
SCC
and Water Chemistry Issues
| D05-2 | The
Inhibition Mechanism and Applicability of Inhibitors for the ODSCC of Alloy 600
Tubing in PWRs Joung Soo Kim, Hong Pyo Kim, Yongsun Yi |
| D05-4 | Corrosion
Monitoring Programmes for Life Time Extension of NPP Components Martin Brezina, Ludovit Kupca, Peter Beno |
| D05-5 | Development
of the Normative Documentation for Control Exploitation Pipe Lines of Second Side
NPP with VVER V.I. Baranenko, S.G. Oleynik, O.A. Belyakov, R.S. Istomin, A.V. Kumov |
Component Integrity
& PTS
| D06-1 | Aging
Management of PWR Internals Components H.T. Tang, Jeff D. Gilreath |
| D06-2 | Proactive
Materials Degradation Assessment (PMDA) Joseph Muscara, Nilesh C. Chokshi, Michael A. Switz |
| D06-3 | Probabilistic
Structural Integrity of Reactor Vessel under Pressurized Thermal Shock Myung Jo Jhung, Young Hwan Choi, Hho Jung Kim, Changheui Jang |
| D06-4 | Technical
Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the
PTS Rule (10CFR50.61) Mark T EricksonKirk, Nilesh C. Chokshi, Roy Woods, Mike Junge, Shah Malik, Dave Bessette |
Materil
Properties Related to Aging
| D07-1 | Life-Time
Prediction of Austenitic Stainless Steel by Applying Magnetic NDT-Methods Markus Niffenegger, Hans J. Leber, Dietmar Kalkhof |
| D07-3 | Have
Any Material Tests Been Forgotten? Josef Jansky |
VVER
Lifetime Management
| D08-1 | Results
from Irradiation Embrittlement Monitoring Programmes of RPV's Operated in the
Slovak Republic NPP's Peter Beno, L'udovít Kupca, Martin Brezina |
| D08-2 | Radiation
Embrittlement of VVER-1000 RPV Steels Yury A. Nikolaev |
| D08-3 | Integrated
Surveillance Specimen Program for WWER-1000/V-320 Reactor Pressure Vessels Milan Brumovsky, Miloš Kytka, Petr Novosad, Jiri ZDárek |
| D08-5 | Flux
Effect on Radiation Embrittlement of VVER-440 Reactor Pressure Vessel Materials Alexandr Kryukov, Anna Chernobaeva, Amir Amaev, Dmitry Erak, Pavel Platonov, Yaroslav Shtrombakh |
| D08-6 | Experience
of Operating the Automatic System of Residual Service Life Monitoring for WWER-1000 A.V. Bogachev, B.N. Dranchenko, V.P. Semishkin, M.B. Bakirov |