| D01/1 |
Lifetime
Management Study on Kori Unit 1
J. S. Kim, I. S. Jeong and T. E. Jin |
| D01/2 |
Major
Components Life Evaluation for Nuclear PLIM Feasibility Study
I. S. Jeong and C. H. Jang |
| D01/3 |
Information
Manager - Modern EDP as a Tool for Safety-Related Plant Evaluation
Christian Dirmeier and Karl Gotz |
| D01/4 |
Ageing
Management in German Nuclear Power Plants
Natalie Bath, Rainer Gersinska, Ralf Hennig, Gunter Holdt and Bernhard
Kociok |
| D01/5 |
Approval
Criteria Pertaining to the Revision of Safety-Related Relevant Testing and
Maintenance Strategies
Torsten Roglin, Karl Gotz and Rainer GroBerichter |
| D01/6 |
Points
of Emphasis in the Supervision of Bavarian Nuclear Power Plants
Jurgen Walther |
| D01/7 |
The
Estimation of Critical RTNDT and Probability of Failure
for PWR Vessels
Sung-Gyu Jung, Hyun-Su Kim, Tae-Eun Jin, Chang-Heui Jang and Il-Seok
Jeong |
| D02/1 |
Latest
Advances in Fatigue Monitoring Technology Using EPRI's FatiguePro Software
Gary L. Stevens, David A. Gerber and Stan T. Rosinski |
| D02/2 |
Thermal
Loading Phenomena and Monitoring for Material Fatigue in Nuclear Power Plants
H. J. Golembiewski and W. Kleinoeder |
| D02/3 |
Establishment
of Simplified Fatigue Evaluation Method by Green's Function
Hideki Fujimoto, Yasushi Kanazawa and Yuji Takahashi |
| D02/4 |
Fatigue
Analysis of Modified Main-Steam Isolation Valve for Yonggwang Nuclear Units
1 & 2
Due Yule Chung, Tae Soo Hahn and Weon Seo Park |
| D02/5 |
Thermal
Fatigue in Piping Tees - Cost Effective Methods for Assessment
Urs Blumer and Daniels Humair |
| D02/6 |
A Study
of Simplified Fatigue Evaluation Method Based on Operating Data
Yuji Takahashi, Yuichi Okamura, Yasuchi Kanazawa, and Naoki Kojima |
| D03/1 |
Steam
Generator Internals Design Review Part I: Bundle Wrapper Studies / Status
and Perspective
Jean-Paul Gauchet, Francis Munoz, Eric Molinie, Bernard Bussy and
Nicolas Gillet |
| D03/2 |
SG Internals
Design Review Part II: SG Wrapper Drop Safety Studies
Gilles Poudroux, Nicolas Gillet, Jean-Paul Gauchet, Marc Petit and Francis
Munoz |
| D03/3 |
SG Internal
Design Review Part III: Corrective and Preventive Maintenance and in Service
Surveillance of Steam Generator Bundle Wrappers
Francis Munoz, Jean-Paul Gauchet, Marc Stindel, Christine Dabere and
Alain Pradel |
| D03/4 |
Steam
Generator Tube Integrity Testing/Analysis
Kenneth E. Kasza, Saurin Majumdar and Joseph Muscara |
| D04/1 |
Safety
and Availability - RAM Analysis in Power Plants
Sven Bohringer and Karl Gotz |
| D04/2 |
Reliability
Appraisal for a PWR Auxiliary Feed-Water System under Aging by Point Processes
Hector C. Noriega, Pedro L. C. Saldanha and Paulo Fernando Frutuoso e
Melo |
| D04/3 |
Material
Properties for In-Service Inspection RSE-M Code Flaw Evaluation
Bruno Barthelet and Franfois Faure |
| D04/4 |
Preliminary
Investigation on the In-Service Inspection of Graphite Components in the
HTTR Using Ultrasonic Testing
Masahiro Ishihara, Taiju Shibata and Satoshi Hanawa |
| D04/5 |
Genetic
Algorithm Application to Making up Economic Maintenance Schedule
Takeshi Takao and Shinichi Ohki |
| D05/1 |
Ageing
Management in Nuclear Power Plant Beznau
Suresh Sahgal |
| D05/2 |
Material
Property Determination of Aged Cast Austenitic Stainless Steel Components
for LBB Application
Seung-Gun Lee, Yoon-Suk Chang and Tae-Eun Jin |
| D05/3 |
Four-Point
Bending Test of Aged Cast Duplex Stainless Steel Pipes
Takeharu Nagasaki, Masayuki Tabata, Hitoshi Mizuta, Koji Koyama and ham
Muroya |
| D05/4 |
Prediction
of PWSCC Growth Rate for Alloy 600 by Artificial Neural Network
Jong-Sung Kim, Seung-Gun Lee, Tae-Eun Jin andKang-Yong Lee |
| D05/5 |
Modelling
of Cirus Graphite Reflector with Stored Energy: Comparison of Blind Predictions
with High Power Measurements
B. K. Dutta, H. S. Kushwaha, V. Venkat Raj, S. Sankar and S. K. Sharma |
| D06/1 |
Evaluation
of Korean Next Generation Reactor Vessel Neutron Fluence by Full-Scope Monte
Carlo Calculations
Jong Kyung Kim, Bo Kyun Seo, Chang Ho Shin and Jae-Hun Lee |
| D06/2 |
The
Development of Reactor Pressure Vessel Thermal Annealing Evaluation Program
for NPP Lifetime Management
Jin-Seok Park, Heui-Young Roh, Chae-MookLee and Tae-Eun Jin |
| D06/3 |
Evaluation
of Flow Stress by Neural Networks and Simulated Annealing Methods
Jin Sik Cheon and Cheol Hong Joo |
| D07/1 |
Nuclear
Power Plant Containment Pressure Boundary Aging Research
Dan J. Naus, Bruce R. Ellingwood, Jeffery L. Cherry, Nilesh C. Chokshi
and James F. Costello |
| D07/2 |
Activities
of the OECD Nuclear Energy Agency in the Area of Concrete Containment Ageing
Alex G. Miller and Leslie M. Smith |
| D07/3 |
Prediction
of Long-Term Natural Degradation Behavior of Atomic Reactor Container's
Non-Metallic Liners
Jae-RockLee, Soo-Jin Park, Sang-Jo Kim, Tae-Wan Yang and Sang-Kook Lee |
| D07/4 |
Material Issues
in Manufacturing and Operation of Transport and Storage Spent Fuel Casks
Jiri Brynda, Pavel Hosnedl, Miroslav Jilek and Miroslav Picek
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