17th International
Conference on
Structural Mechanics
in Reactor Technology
|
17th International
Conference on |
|
DIVISION M: STRUCTURAL RELIABILITY
AND PROBABILISTIC
SAFETY ASSESSMENT (PAS)
M01 - Probabilistic Analysis in Dynamic and Impact Mechanics
| M01-1 |
Reliability-based
Approaches for Safety Margin Assessment in the French Nuclear Industry
(M483) |
| M01-2 | Simplified
Estimation Method for First Excursion Probabiliti of Secondary System with
Friction (M354) Shigeru Aoki |
| M01-3 | Reliability
Assessment of Structural Impact/Contact Mechanics (M208) K. Petkevicius, R. Kulak, P. Marchertas |
| M01-4 | Reliability Analyses
of Pipe Whip Impacts (M268) Robertas Alzbutas, Gintautas Dundulis, Ronald F. Kulak, Paul V. Marchertas |
| M01-5 | Statistical Analysis of
Real Flight Tracks for the Risk Assessment of a New Takeoff-Route
(M293) Birgitt Felbermeier, Gerhard Klein, Jens Döring |
| M01-6 | Risk-based Safety Performance
Indicators for Nuclear Power Plants (M212) S. Chakraborty, Y. Flodin, G. Grint, H. Habermacher, A. Hallman, R. Isasia, Z. Karsa, M. Khatib-Rahbar, K. Koeberlein, N. Matahri, E. Melendez, I. Moravcik, J. Preston, G. Prohaska, C. Schwaeger, M. Tkac, E. Verduras |
M02 - PSA for Seismic
and Other External Events
| M02-1 |
Probabilistic Liquefaction
Hazard Evaluation: Method and Application (M164) |
| M02-2 | Development
of Seismic Hazard Curves for the Portfolio of Facilities (M047) Sei'ichiro Fukushima, Harumi Yashiro |
| M02-3 | Seismic Fragility Analyses
of Nuclear Power Plant Structures Based on the Recorded Earthquake Data
in Korea (M040) Yang Hee Joe, Sung Gook Cho |
| M02-4 | Assessment
of Structural Safety under Seismic Hazard by Vulnerability Functionals
(M035) Adrian Vulpe, Alexandru Carausu , George Emanuel Vulpe |
| M02-5 | Seismic PSA for NPP Paks
of Hungary (M513) Attila Bareith, Zoltán Karsa, John W. Stetkar |
| M02-6 | Maximum Fragility Analysis
of Loviisa Nuclear Power Plant Ventilation Stack for Wind Loads
(M341) Pentti Varpasuo |
M03 - Reliaility
Analysis of Pressure Vessels and Piping
| M03-1 |
Probabilistic
and Deterministic Treatments for Multiple Flaws in Reactor Pressure Vessel
Safety Analysis (M222) |
| M03-2 | Probabilistic
Procedure to Evaluate Integrity of Degraded Pipes under Internal Pressure
and Bending Moment (M118) Eberhard Roos, Karl-Heinz Herter, Peter Julisch, Frank Otremba, Xaver Schuler |
| M03-3 | Development
on Methods for Evaluating Structure Reliability of Piping Components
(M401) Thomas Schimpfke, Hans Grebner, Jörg Peschke, Jürgen Sievers |
| M03-4 | Probabilistic
Assessment of Fatigue Damage Including Statistical Uncertainties in S-N
Curves (M232) Bruno Sudret, Zakoua Guédé, Patrick Hornet, Jean-Michel Stéphan, Maurice Lemaire |
| M03-5 | Risk
Based Lifetime Assessment of Piping under Creep-Fatigue Conditions (M495) Ondrej Bielak, Vladimír Bína, Jan Korouš |
| M03-6 | A
Pilot Study of RI-IST Applications to IST Check Valves for Ulchin Unit 3
(M140) Daeil Kang, Kilyoo Kim, Jooneon Yang |
M04 - Reliability Analysis of
Concrete Structures and Other Components
| M04-1 |
Containment
Reliability and Risk-Informed Decision Making-A Perspective (M456) |
| M04-2 | Reliability
of the Repairing of Double Wall Containment Vessels in the Context of Leak
Tightness Assessment (M264) Bruno Sudret, Marc Berveiller, Grégory Heinfling |
| M04-3 | Reliability
Assessment of a Reinforced Concrete Beam Subjected to Corrosion (M529) Bruno Capra, Olivier Bernard, Bruno Gérard, Brian Adey |
| M04-4 | Probabilistic
Safety Assessment of the Steam Generator Cover (M449) Stanislav Vejvoda, Zbynek Kersner, Drahomir Novak, Bretislav Teply |
| M04-5 | Probability
Finite Element Assessment Method for Nuclear Graphite Components (M096) Suyuan Yu, Haiyan Li, Chaoyang Wang, Zhensheng Zhang |
| M04-6 | A
Probabilistic Failure Assessment of a Dry Cask Storage System (M480) Cayetano Santos, Douglas Kalinousky, Christopher Ryder, Lee Abramson, Syed Shaukat, Jason Schaperow, Alan Rubin |