7th International
Conference on
Structural Mechanics
in Reactor Technology
|
7th International
Conference on |
|
DIVISION M: RELIABILITY AND
RISK ANALYSIS OF
NUCLEAR POWER PLANTS
M1 - Stochastic Fracture Mechanics and Dynamics
M2 - Load Combinations
| M2/1 |
Combined Dynamic Effects of Correlated Load Processes |
| M2/2 | Partial Safety Factors for
Combined Loading F. Casciati |
| M2/3 | Estimation of Structural Reliability
Under Combined Loads M. Shinozuka, T. Kako, H. Hwang, P. Brown, M. Reich |
| M2/4 | Evaluation of Concurrent Peak
Responses P.C. Wang, J. Curreri, M. Reich |
| M2/5 | Probabilistic Response Spectrum
Method for Multidirectional Seismic Input A. Der-Kiureghian, W. Smeby |
| M2/6 | Load Combination for the Primary
Pipe of a PWR P. Kafka, G. Zipf, R. Schäfer |
| M2/7 | A Probabilistic Concept for
the Aseismic Design of Nuclear Power Plants G. König, D. Hosser |
M3 - Quality Assessment and Reliability I
| M3/1 |
Damage Evaluation for Structural Reliability Assessment |
| M3/2 | Structural Modelling and Limit
State Identification for Reliability Analysis of RC Containment Structures M. Chang, P. Brown, H. Hwang, T. Kako |
| M3/3 | Uncertainty Analysis of Containment
Resistance Subjected to Seismic Loading L.F. Greimann, F.S. Fanous, D.D. Ketelaar |
| M3/4 | A Method for Estimating Fragility
Curves Using Expert Opinions A. Mosleh, G. Apostolakis |
| M3/5 | Evaluation of an Expert Opinion
Survey to Determine Component Seismic Fragility V.N. Vagliente, M. Voutyras, A. Curtis |
| M3/6 | Uncertainty Evaluation of Fast
Reactor Core Seismic Response A. Martelli, M. Forni, A. Amendola, A.C. Lucia, G. Maresca |
| M3/7 | Failure Probabilities of LMFBR-Components
Under Extreme-Load Conditions H. Schulz, M. Glahn, S. Beliczey |
| M3/8 | Probabilistic Analysis of Turbine
Missle Damage to Nuclear Power Plant Structures L.A. Twisdale, W.L. Dunn, R.A. Frank |
M4 - Quality Assessment and Reliability II
| M4/1 |
The Effect of Quality Control on Reliability Estimation |
| M4/2 | Reliability Studies of Bored
Concrete Pile Foundations J.D. Riera, F.C.P. de Barros |
| M4/3 | Integrity and As-Built Capacity
of Bored Pile Group D. Shaw, J.F. Kissenpfenning, M.R. Hümmer |
| M4/4 | Probabilistic Seismic Analysis
of Slender Infinite Burried Structures J. Goodman, J.E. Koch |
| M4/5 | Probabilistic Analysis of
a Nuclear Auxiliary Building on Aseismic Bearing Pads N.R. Vaidya, M.D. Snyder, A.J. Eggengberger |
| M4/6 | Inspection of Small Samples of Nominally Identical,
High Integrity Components G.O. Johnston |
| M4/7 | Stochastic Finite Element Analysis
of Uncertain Intrinsic Stresses T. Hisada, S. Nakagiri, T. Nagasaki |
| M4/8 | Reliability Analysis for Stiff
Versus Flexible Piping Systems S.C. Lu, C.K. Chou |
M5 - Structural Systems/Component Reliability
| M5/1 |
Reliability Assessment of Nuclear Structural Systems |
| M5/2 | Interaction of Structural and
Component Reliability G.I. Schuëller |
| M5/3 | Development of a Reliability
Analysis Method for Category 1 Structures M. Shinozuka, T. Kako, H. Hwang, M. Reich |
| M5/4 | Logic Flowgraph Methodology
for Use in Disturbance, Reliability and Risk Analysis S. Guarro, D. Okrent |
| M5/5 | Dynamic Simulation Model for
PWR M. Motamed, D. Okrent |
| M5/6 | The Contribution of Control
Systems in LWR Safety J. Alter, D. Okrent |
| M5/7 | Application of the SSMRP Methodology
to the Seismic Probabilistic Risk Analysis at the Zion Nuclear Power Plant M.P. Bohn, L.C. Shieh, J.E. Wells, L.L. George, R.W. Mensing, L.E. Cover, D.L. Bernreuter, J.J. Johnson |
| M5/8 | Structural/Piping Sensitivity
Studies for the USNRC Seismic Safety Margins Research Program L.C. Shieh, W.J. O'Connell, J.J. Johnson |
| M5/9 | Seismic Risk Analysis for the
Fast Breeder Prototype SNR-300 in Kalkar (FRG) D. Hosser |
M6 - Risk Studies
| M6/1 |
Use of PRA and Safety Goals in Nuclear Power Plant
Regulation |
| M6/2 | German Risk Study of PWR's P. Kafka |
| M6/3 | PRA and the Implementation
of Quantitative Safety Goals D. Okrent |
| M6/4 | Lessons Learned from Seismic
PRA Studies M.K. Ravindra, R.P. Kennedy |
| M6/5 | PRA Has Many Faces - Can the
Safety Goal be Well-Posed? H. Bargmann |
| M6/6 | Study of the Accidental Risk
of the German Fast Breeder Prototype Reactor SNR-300 K. Koeberlein |
| M6/7 | Probabilistic Seismic Design
of a Dedicated Shutdown Heat Removal System Including Benefit Considerations Y.T. Lee, D. Okrent |
| M6/8 | Reliability Analyses to Detect
Weak Points in Secondary Plants R. Schiling |