| D01/1 |
Nuclear
power plant Generic Aging Lessons Learned (GALL)
G. Regan |
| D01/2 |
The
main mechanisms of the degradation of material properties in the process
of NPP equipment operation
I.V. Gorynin and B.T. Timofeev |
| D01/4 |
Technical
information from industry reports addressing license renewal
C. Regan |
| D02/1 |
Reactor
pressure vessel annealing-effective mitigation method
M. Brumovsky and J. Brynda |
| D02/2 |
Reactor
pressure vessel annealing demonstration evaluation
W.E. Pennell, B.R. Bass, J.A. Keeney, C.B. Oland, L.J. Ott, S.N. Malik
and M.A. Mitchell |
| D02/3 |
Test
results of aged cast austenitic stainless steel elbows
S. Sahgal, T.R. Mager, C.C. Kim and D.C. Bhowmick |
| D02/4 |
Improvement
of residual stress on material surface by water jet peening
K. Hirano, K. Enomoto, M. Mochizuki, M. Hayashi, E. Hayashi and S. Shimizu |
| D02/5 |
Evaluation
of plastic deformation in austenitic stainless steel by positron annihilation
N. Nakamura, M. Uchida, K. Yoshida and M. Takimoto |
| D02/6 |
Cracking
behavior and positron annihilation measurement during fatigue damage in
austenitic stainless steel
N. Nakamura, M. Uchida, C. Fukuoka and K. Yoshida |
| D03/2 |
Detection
of material degradation in nuclear power plant components by Eddy current
method
N. Maeda and G. Yagawa |
| D03/3 |
Nondestructive
testing by thermoelectric power measurements
J.M. Leborgne, S. Miloudi, R. Borrelly, O. Grisot and J.P. Massoud |
| D03/4 |
Progress
and effectiveness improvement of ISI for VVER type primary circuit components
L. Horacek and J. Zdarek |
| D03/5 |
Utilisation
de "CIVAMIS" pour la caractérisation de défauts
détectés dans les cuves R.E.P.
F. Lasserre, L. Hemandez, L. Paradis and F. Champigny |
| D04/1 |
Steam
generator tube support plate degradation - French experience
J.P. Gauchet, J. Salin, F. Munoz and J. Ph. Frontigny |
| D04/2 |
Structural
mechanics assessment of a core shroud with cracking
R. Engel, H.J. Lomoth, and K.M. Pulschen |
| D05/1 |
Axisymetrical
modelling of operating stresses in 900 MWe steam generator rolled tubes
I. Eymard, F. Voldoire, B. Flesch and H. Gamha |
| D05/2 |
Upgrading
of PTS assessment for WWER 440 / 230 reactor pressure vessels - The case
of Kozloduy 1
M. Erve, Y. Dragunov, I. Gledatchev, Ph. Monette and C.Y. Rieg |
| D06/2 |
Ultrasonic
control system for Superphenix steam generator tubes
G. Moreau, R. Bargain, M. Bonmartin, N. Rigaud, Ph. Benoist and A. Bosio |
| D06/4 |
Development
of inservice inspection method for graphite components by micro-indentation
technique in the HTTR
M. Ishihara, J. Aihara and T. Oku |
| D06/5 |
A study
on fracture characteristics of CANDU pressure tube by small punch test
S.H. Nho, J.W. Ong, H.S. Yu and K.M. Oh |
| D07/1 |
Fatigue
lives of stainless steels in PWR primary water
H. Kanasaki, R. Umehara, H. Mizuta and T. Suyama |
| D07/2 |
Effects
of strain rate and temperature change on the fatigue life of stainless steel
in PWR primary water
H. Kanasaki, R. Umehara, H. Mizuta and T. Suyama |
| D07/3 |
Allowable
temperature rise and lowering rates during startup and shutdown for FBTR
K. Venkataramana, P. Chellapandi, S.C. Chetal and S.B. Bhoje |
| D07/4 |
Analysis
of cracks in thermal barrier cover of 900 MW PWR primary pumps
F. Ribes and V. Maupu |
| D07/5 |
Fatigue
evaluation of 220MWe PHWR coolant channel sealdisc
S.K. Gupta, D.S. Chawla, H.S. Bhambra and H.S. Kushwaha |
| D08/1 |
Integrity
assessment of mechanical components and fatigue life prediction under multiaxial
variable amplitude loading
B. Kenmeugne, J.C. Clement, P. Morilhat and J.L. Robert |
| D08/2 |
Fatigue
life evaluation of major components for nuclear power plant lifetime management
C. Jang, I.S. Jeong, S.Y. Hong, T.E. Jin and S.G. Jung |
| D08/3 |
Regulatory
damage monitoring of the liquid metal reactor SUPERPHENIX
M. Phelip, P. Darde, M. Tatone, M. Nagel and M. Richard |
| D08/4 |
Fatigue
monitoring system using the inverse problem method and extended Green's
function method
K. Hojo, M. Ochi, T. Umakoshi and M. Yabuno |
| D08/5 |
Finite
element based fatigue monitoring system
N.K. Mukhopadhyay, B.K. Dutta, P.S. Prasad, and H.S. Kushwaha |
| D08/6 |
Comptabilisation
des situations: retour d'expérience et nouvelle méthode
E. Bouquerel and D. Savoldelli |
| DW/2 |
Cuve de réacteurs
nucléaires
PWR E.D.F. contrôle R.D.C. (Researche de défauts
de corrosion)
J.C. Barbant, P. Bastin, M. Piriou, J. Sagnier, M. Serre and T. Sollier
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