10th International
Conference on
Structural Mechanics
in Reactor Technology
|
10th International
Conference on |
|
DIVISION D: PERFORMANCE AND LIFE EXTENSION OF OPERATING REACTORS
(The papers with links are those received by the SMiRT 10 Secretariat at the
time the Transactions went to press)
D01: Fatigue Assessment
|
Effect of Residual
Stresses and Complex Loadings on the Fatigue Behavior of Underclad Clads |
| Long-Term
Vibration Trending as a Basis for Performance Assessment and Life Extension
of Mechanical Components D. Wach, R. Sunder |
| Fatigue
Behavior of Welded Junctions Submitted to Thermal Shocks J.C. Masson, D. Moinereau, M. Rioland |
| In-Service
Lifetime Monitoring of Piping Systems Taking into Account External Forces
and Moments Besides Internal Pressure and Temperature F. Bietenbeck, K. Rohler |
D02: Fatigue Monitoring
| A
New Approach for NSSS Fatigue Life Assessment G. Bimont, G. Cordier |
| FRAMATOME
Operating Transients Monitoring System Used for Equipment Mechanical Surveillance B. Boneh, J. Heliot, R. Fritz |
| SAUL
Program for On-Line Analysis of Stresses and Fatigue on Structures L. Lazzeri, M. Scala, M. Agrone, S. Cecconi, P. Caorsi |
| Vibration
Monitoring of the Primary Piping System During the Hot Functional Tests
of the Mulheim-Karlich PWR V. Bauernfeind, Th. Bloem, W. Pache, H.J. Diederich |
| Preoperational
Testing Procedure for Vibration of Piping Systems M. Lepiece, C. Leblois |
D03: Reactor Internals
|
Belgian Experience
on Reactor Core Internals |
| Aging
Degradation of BWR Reactor Internals Arthur G. Ware |
| Model
for the Spread of Contact Between Pressure Tube and Calandaria Tube R.A. Holt, N. Badie, S. Unterbergs |
D04: Erosion/Corrosion
|
Acceptance
Criteria for Structural Evaluation of Erosion/Corrosion Thinning in Carbon
Steel Piping |
| Evaluation
of Erosion/Corrosion Damage at Two Nuclear Power Plants Carl J. Czajkowski |
| Erosion/Corrosion
in Power Plant Single- and Two-Phase Flow Experience, Prediction, NDE Management N. Henzel, D.C. Crosby, S.R. Eley |
| Engineering
Evaluation of Erosion/Corrosion in Piping Systems C.S. Hoemann, E.G. Berak |
| Flow
Assisted Corrosion: The Different Ways to Avoid Damage F.N. Remy, M. Bouchacourt |
D05: Life Extension and Aging
| Application
of Annealing for WWER Vessels Life Extension Vladmir I. Badanin, Yuri G. Dragunov, Valentin G. Fedorov, Igor V. Gorynin, Vladimir A. Nickolaev |
| Fitness-for-Service
as the Technical Basis for Nuclear Plant Life Extension Jeff D. Byron, John J. Carey |
| Selective
Investigation of As-Found Design, Construction, Maintenance and Aging in
Nuclear Power Plants Fred A. Webster |
| The
Trending of Aging Parameters Frank E. Gregor |
| Use
of the Cylindrically Guided Wave Technique for Inspection of Stud Bolts,
Valve Stems and Pump Shafts Glenn M. Light, Edward A. Bloom, Edward H. Ruescher, Soung-Nan Liu |
| Optimization
of Reactor Pressure Vessel Surveillance Program Analysis W.B. Waeber, U. Zimmermann, G. Solt, P. Tipping |
D06: Steam Generator Experience
| Behaviour
of Steam Generator Tubes in Belgium and their Consequences G. Roussel, P. Mignot |
| In-Service
Stresses in 900 MWe PWR Steam U-Bends B. Flesch, M. Guttmann, P. Vidal, J. Vagner |
| A
Predictive Model for Steam Generator Degradation Through PW SCC in Roll
Transitions Paul Hernalsteen |
| Remedies
for PWR Recirculating Steam Generator Tube Failures A.S. Amar, V.N. Shah |
| Finite
Element Calculation and Direct X-Ray Diffraction Measurement of Residual
Stresses Induced by an Hydraulic Expansion in Steam Generator Tubes During
the Sleeving Process C. Leblois, M. Gyuette, G. Platbrood |
D07: Aging of Concrete Structures
| Structural
Aging Program to Assess the Adequacy of Critical Concrete D.J. Naus, M.F. Marchbanks, C.B. Oland, E.G. Arndt |
| The
Effect of High Temperature on the In-Situ Condition of PVC Waterstop J.J/ Deans, J.A. Sato, P.D. Bhat |
| Inspection
and Mitigating Measures for Life Extension of Nuclear Power Plant Containment
Structures B.L. Meyers, M.A. Daye |
| GEOMAN:
A Knowledge Based Expert System for On-Line Monitoring of Nuclear Structures M.G. Cremonini, C. Vardanega, M. Mirone, E. Saveri |
| In-Depth
Analysis of Eight Criteria for Integrated Leakage Rate Tests for Nuclear
Power Plant Containment Buildings William T. Wagner, James P. Langan, Wallace F. Norris, Dan Lurie |
D08: Learning from Chernobyl
| Peculiarities
of Nuclear Fuel Inside Confinement System of Chernobyl NPP Damaged Reactor S.T. Belyaev, A.A. Borovoy, A. Yu. Gagarinsky |
| Some
Aspects of the Genetic Consequences of the Chernobyl Diaster V.A. Shevchenko |
| Theoretical
Analysis and Numerical Modeling of Heat Transfer and Fuel Migration in Underlying
Soils and Constructive Elements of Nuclear Plants During an Accident Release
from the Core R.V. Arutunjan, L.A. Boshov, V.V. Vitukov, V.M. Gooviznin, F.M. Dykhne, V.P. Kiselev, S.V. Klementova, I.E. Krayushkin, A.V. Moskovchenko, V.D. Pismennii, A.G. Popkov, S.Y. Chernov, V.V. Chudanov, O.V. Khoruzhii, A.I. Yudin |
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