| L01/1 |
Experiments and Constitutive
Modelling for Uniaxial Ratchetting of 316 FR Steel at Room Temperature
Nobutada Ohno, Mohamed Abdel-Karim and Mamoru Mizuno
|
| L01/2 |
Cyclic
Inelastic Behavior and Cre~-Fatigue Life Prediction of Perforated Plates
Toshihide Igari, Shinichi Nomura and Yoritaka Mizokami |
| L01/3 |
Cyclic
Creep ofHeat-Resistant Steel 10 GN2VFA Takmg Into Account a Number of Operational
Factors for NPP Steam Generators
Felix R Giginyak |
| L01/4 |
On Viscoelastoplastic
Thermomechanical Constitutive Patterns of Inelastic Materials
G. Bles, S.P. Gadaj, P. Guelin, W.K. Nowacki and A.Tourabi |
| L01/5 |
Failure
Strain of the Reactor Pressure Vessel Head under Impact Loading: Experiments
on Scale Influence
T. Jordan and T. Malmberg |
| L01/6 |
Generalisation
of Inelastic Cons.itutive Models foiAutomated Parameter Identification
Tomonari Furukawa, Tomohiro Sugata, Shinobu Yoshimura and Genki Yagawa |
| L02/1 |
Caustic
Stress Corrosion Cracking of Ni Base Alloys
H.P. Kim, S.S. Hwang, I.H. Kuk and J.S. Kim |
| L02/2 |
Evaluation
of Steam Generator Tube Materials Being Used at Korean NPPs
J.H. Han, D.H. Lee and J. S. Kim |
| L02/3 |
Effect
of Lead on the Passive Film on Alloy 600 and Alloy 690 in High Temperature
Water
Seong Sik Hwang, Hong Pyo Kim, Il Hiun Kuk and Joung Soo Kim |
| L02/4 |
Hydrogen Uptake and Corrosion
Behavior of Zr-2.5 Nb Pressure Tubes in Wolsung Unit 1
Kee Nam Choo, Sang Chul Kwon, Sung Soo Kim, Yong Moo Cheong and
Young Suk Kim
|
| L02/5 |
Characterization
of Korean-Made Prototypical Inconel Tube Materials for Steam Generators
in Nuclear Power Plants
Joung Soo Kim, Jin Sung Jang, Duk Hyun Lee, Hong Pyo Kim and Il Hiun
Kuk |
| L02/6 |
The
Effect of Compressive Residual Stress on the Primary Water Stress Corrosion
Cracking of Alloy 600 TI Steam Generator Tubings
In-Gyu Park |
| L03/1 |
Influence
of Damage Field on Asymptotic Stress Field of a Creep Crack
Mamoru Mizuno, Sumio Murakami, Toshiyuki Hirano and Yan Liu |
| L03/2 |
Comparison between Numerical
Predictions and Experimental Observations of Creep Damage on a Cylinder
under Internal Pressure and Axial Thermal Gradient
S. Bhandari, P. Dupas, L. Le Ber, L. Nicolas and R.E. Henry
|
| L03/3 |
Creep and Rupture Modeling
by Damage Mechanics
Ilsup Chung and Young S. Chai
|
| L03/4 |
Environmental
Effects on Fatigue, Creep and Creep-Fatigue Behavior of 316FR Steel
Yukio Takahashi, Yuji Toya and Hideaki Abe |
| L03/5 |
Cavity
Formation in Interface between Power Low Creep Particle and Elastic Matrix
Subjected to a Uniaxial Stress
Yong-Son Lee, Sang-Tae Kim, Jae-Do Kwon and Kil-Soo Kim |
| L03/6 |
Creep
Damage Analysis Using the Gurson Model on Welded Joints of Mod. 9Cr-l Mo
Steel
Fumio Takemasa, Akihiko Suzuki and Koutarou Itou |
| L04/1 |
New Approach Applied for Irradiation
Embrittlement Monitoring of WWER-440/213 Type Reactor Pressure Vessels
Ludovit Kupca, Peter Beno and Miroslav Herman
|
| L04/2 |
On the
Mechanics of Fuel Fretting Problem
Hyung-Kyu Kim |
| L04/3 |
Thermal
Recovery Characteristics of Neutron-Irradiated UJ-2 Reactor Pressure Vessel
Steel Forging Steel
Se-Hwan Chi and Kee-Ok Chang |
| L04/4 |
The
Effects of Thennal Aging on Material Behavior and Strength of CF8M in Nuclear
Reactor Coolant System
Jae-Do Kwon, Joong-Cheul Park, Yong-Son Lee, Woo-Ho Lee and Yun-Won
Park |
| L04/5 |
Creep-Fatigue
and Fatigue Crack Growth Properties of 316 LN Stainless Steel at High Temperature
Wan-Young Maeng and Young-Hwan Kang |
| L04/6 |
Study
on y-Ray Induced Embrittlement of Light Water Reactor Pressure Vessel
Steel
Tohru Tobita, Masahide Suzuki, Yoshio Idei, Akihiro Iwase and Kazuya
Aizawa |
| L05/1 |
Characteristics
of Nb Containing Zirconium Alloys with a Variable of Manufacturing Process
Young Suk Kim, Kyung Soo Yim, Sang Chul Kwon, Sung Soo Kim and Kee
Nam Choo |
| L05/2 |
Differences
in Mechanical Properties and Microstructure of SA 508 CL. 3 Reactor Pressure
Vessel Steels Manufactured by Different Steel Refining Process
Se-Hwan Chi and G. E. Lucas |
| L05/3 |
Effects
of Long-Tenn Aging and Sensitization Heat Treatments on the Microstructure
of Ni-Base Alloy 600 Surface-Melted by a CO2 Laser Beam
Yun Soo Lim, Hong Pyo Kim, Hai Dong Cho, I1 Hiun Kuk and Joung Soo
Kim |
| L05/4 |
Modelling
Phase Transfonnation in Welding Simulation
J. Kichenin, X Pinelli, J. Frelat and T. Charras |
| L05/5 |
Contribution to the Validation
of the Models Related to the Prediction of the Heat Affected Zone Behavior
Nathalie Cavallo, Lakhdar Taleb, Francois Waeckel, Francois Colonna
and Daniel Dubois
|
| L05/6 |
Reduction of Residual Stress
by Ultrasonic Vibration During Welding
Tadashi Nishimura, Shigeru Aoki, Tetsusmaro Hiroi and Seiji Hirai
|
| L06/1 |
Deformation Behavior of Zr-2.5%
Nb Pressure Tube Material
Sung Soo Kim, Young Suk Kim, Sang Chul Kwon, Sang Bok Ahn and Ki
Nam Choo
|
| L06/2 |
High Temperature Behaviors of
Type 316L(N) Stainless Steel
Woo-Seog Ryu, Dae Whan Kim, Woo Gon Kim and Il-Hiun Kuk
|
| L06/3 |
Technique for an Evaluation
of Anisotropy of Mechanical Properties of Industrial Items
Igor V. Matsegorin, Evgeni Yu Rivkin and Alexandre N. Semenov
|
| L06/4 |
Better Understanding of Delayed
Hydride Cracking in Zr-2.5Nb Pressure Tube
Sang Chul Kwon, Yong Moo Cheong, Sung Soo Kim, Ki Nam Choo and
Young Suk Kim
|
| L06/5 |
Investigations on Size Effects
in Ferritic and Austenitic Materials
T. Malmberg, K. Krompholz, G. Solomos and E.C. Aifantis
|
| L06/6 |
Measurement
and Modelling of Stress Relaxation Near a Notch in Zr-2.5 Nb
Brian Leitch, Nicholas Christodoulou and John Root |
| L06/7 |
Dislocation
Pileup Model for Back Stress Evolution in Crystalline Plasticity
Tradashi Hasebe and Yutaka Imaida |
