7th International
Conference on
Structural Mechanics
in Reactor Technology
|
7th International
Conference on |
|
DIVISION D: OPERATING REACTOR STRUCTURAL EXPERIENCE
D1 - Piping
| D1/1 |
Vibration Induced Failures in Nuclear Piping Systems |
| D1/2 | Thermal Fluctuations in Mixing
Tees (Experiences, Measurements, Prediction and Fixes) A. Nordgren |
| D1/3 | Fatigue Cracking in BWR Feed Water Piping
Due to Thermal Fluctuations S. Andersson |
| D1/4 | Fast Diagnosis and Treatment
of Cracklike Defect Injuriousness in PWR Power Plant Equipment B. Boneh, Ph. Gilles, M. Benchimol |
| D1/5 | Residual Stresses of Girth
Butt Welded Pipes and Its Improvement T. Shimizu, K. Enomoto, S. Sakata, W. Sagawa |
| D1/6 | Probabilistic Risk Assessment
of Weld Quality in Steel Piping Under Seismic Conditions N.G. Awadalla, D.A. Crowley, W.F. Yau |
| D1/7 | A Statistical Approach to the
Analysis of ISI Data Using the Bayes Method O.J.V. Chapman |
D2 - Reactor Pressure Vessel Experience
| D2/1 |
Severity, Causes, and Frequencies of Pressure Vessel
Thermal Shock at U.S. PWR Plants (1963-1981) |
| D2/2 | Impact of Plant Operating Experience
on Design Considerations for Reactor Vessel Integrity T.A. Meyer, K.R. Balkey, D.R. Sharp, J.A. Rumancik, H.V. Julian |
| D2/3 | Reactor Pressure Vessel Integrity
and In Service Inspection J.-P. Hutin |
| D2/4 | Pressure Vessel Stress Response
Under Stationary Operating Loads and Pressure Tests - Measurements on the
HDR-RPV and Comparison with Calculations K. Kussmaul, E. Krägeloh, R. Stegmeyer, J. Jansky |
| D2/5 | Surveillance of Radiation Embrittlement
of Reactor Pressure Vessels on the Basis of KTA-Safety Standards K.R. Ernst, G. Philip |
D3 - Containment
| D3/1 |
BWR Mark I Containment Suppression Chamber Structural Reevaluation |
| D3/2 | Structural Evaluation of Mark
I Containment for Hydrodynamic Loads K. Wichman, N. Subramonian, A.A. Gonzalez |
| D3/3 | Evaluation of SRV Pipe Failure
Rtes Via Probabilistic Mechanical Design J.R. Lehner, C. Economos |
| D3/4 | Structural Integrity and Integrated Leak Rate
Tests of Nuclear Containments, Instrumentation Requirements, and Containment
Behavior T.M. Brown, R.J. Krause, P.W. Linehan, L.F. Estenssoro |
| D3/5 | Structural Integrity Testing of Post-Tensioned
Concrete Containments C.N. Krishnaswamy, B.A. Erler |
| D3/6 | Acceptance Criteria for Inservice Inspection
of Post-Tensioning Tendons C.N. Krishnaswamy, S. Putman, B.A. Erler |
| D3/7 | Containment Structure Tendon
Investigation J.F. Fulton, K.H. Murray |
| D3/8 | Assessment of Structural Behaviour of MAPP-1 Containment from Pressure Test T.V.S.R. Appa Rao, A.G. Khadakkar, G.J. Rao, T. Narayanan, T. Sambandam, M.R. Iyer |
| D3/10 | Safety/Relief Valve Loads on BWR Containment
Structures Tsung Ming Su |
D4 - Other Components
| D4/1 |
Valve Problems: Qualification and Reliability - The Experience of
Electriciteé de France |
| D4/2 | Survey of Valve Operator-Related
Events Occurring During 1978, 1979, and 1980 E.J. Brown, F.S. Ashe |
| D4/3 | Investigation of Intergranular Stress Corrosion
Cracking (ICSCC) in Reactor Pumps Structural Components N.J. Biglieri, J.E. Cearley |
| D4/4 | Strucural Integrity and Operability Analysis
of Vertical Pump-Motor Assemblies J.S. Mokri, W.H. Fleming |
| D4/6 | Recent Development for Improving
the PWR Flexibility to Load Follow and Frequency Control Operation M. Dubourg |
| D4/7 | Re-Evaluation of Turbine Missile
Damage Probability Following Discovery of Stress - Corrosion Cracking in
Low Pressure Turbines A. Squire, E.A. Fredenburg, P.K. Shen |
| D4/8 | Testing of 1/4"Ø
Expansion Anchors in Reparied Concrete C.S. Togni, A.F. Varney, C.M. Coones |
| D4/9 | In-Plant Reliability Data System
(IPRDS) - A Comprehensive Data System of component Maintenance Experience R.J. Borkowski, W.K. Kahl, J.R. Fragola |
D5 - Steam Generators
| D5/1 |
Explosive Welded Plug Design for Permanent Obturation
of Defectives Steam Generator Tubes in PWR Nuclear Power Plants |
| D5/2 | Evaluation of a Steam Generator
Tube Repair Process Using an Explosive Expansion Technique at TMI-1 J. Rajan, T.A. Shook, L. Leonard |
| D5/3 | Three Mile Island Unit - 1 OTSG Tube Integrity
Evaluation S.D. Leshnoff, F. Erdogan |
| D5/4 | Failure Evaluation of OTSG Auxiliary Feedwater
Internal Headers J.V. Moran, R.J. Morante, J. Holderness |
| D5/5 | 3-D-Analysis of a Steam Generator Feedwater
Nozzle Considering Stratified Flow Conditions R. Schiffer, . Berkefeld, G. Schön |
| D5/6 | Fatigue Analysis of Steam Generator Feedwater
Nozzles Under Actual Operating Conditions M. Miksch, R.A. Braschel |
| D5/7 | Non-Stationary Stresses of Feedwater Piping
Resulting from Thermal Striping at the Interface of Thermal Stratification M. Miksch, G. Schön |
| D5/8 | A Numerical Two-Dimensional
Modelling of Eddy-Currents: An Application to Non-Destructive Test Ch. Rose |
D6 - Plant Evaluations
D7 - Non-LWR's
| D7/1 |
Thermal-Structural Response of EBR-II Major Components
Under Reactor Operational Transients |
| D7/2 | Study of the Conditions Affecting
the Critical Speed of a Rotating Pump Shaft P. Fardeau, J.L. Huet, F. Axisa |
| D7/3 | Stresses Imposed by Coolant
Channel End Shield Interaction V.K. Mehra, R.K. Singh, R.S. Soni, H.S. Kushwaha, A. Kakodkar |
| D7/4 | Thermo-Structural Investigations
of the Fort St. Vrain Reactor Under Operating and Upset Conditions C.A. Anderson, K. Meier, D.R. Bennett |
| D7/5 | Fort St. Vrain PCRV Structural
Response Monitoring and Verification R.A. Gunnerson, K.C. Cheng |
| D7/6 | Finite Element Stress Analysis
of a Gas-Cooled Reactor for Its Reassessment After 25 Years' Operation M. Lowe |
D8 - Monitoring and Detection
| D8/1 |
Transient Monitoring Experience and Development (Surveillance
des transitoires en exploitation - Expérience et développement) |
| D8/2 | Sensitivity of Ex-Core Neutron
Detectors to Vibration of PWR Fuel Assemblies F.J. Sweeney, J.P. Renier |
| D8/3 | Monitoring of Flow-Induced
Fuel Element Vibration at KNK II F. Mitzel, W. Väth |
| D8/4 | Instrumentation Measurements
During Pressure Test on Twenty 900 MM PWR Containments J. Picaut, ... Barre, ... Triay |
| D8/5 | Acoustic Emission Detection
in Stressed Concrete Specimens C. Birac, M. Contre, D. de Prunele, P. Jamet, M. Astruc, M. Kavyrchine |
| D8/6 | Probability Characteristics
of Strain Gauges of Fatique Damage A.P. Gussenkov, O.L. Bandin |