| F01/1 |
Design
and construction rules committee for the EFR - Current status and development
D. Buckthorpe, J.P. Debaene and P. Rathjen |
| F01/3 |
Evaluation
of ratchetting on experimental tests using simplified design rules
M.T. Cabrillat and Y. Meziere |
| F02B/1 |
The
interest of computation to understand dynamic buckling shear experiments
A. G. Combescure |
| F02B/4 |
Seismic
buckling evaluation on the roofdeck of fast breeder reactor
S. Ogiso, M. Takanashi, T. Takahashi, H. Nakamura, K. Yamamoto and H.
Akiyama |
| F03B/1 |
Dynamic
buckling experiments of fluid-structure coupled co-axial thin cylinders
M. Fukuyama, M. Nakagawa, K. Ishihama, Y. Hagiwara and Y. Toyoda |
| F03B/2 |
On buckling strength
of cylindrical shells with openings under seismic loads
H. Fukuyoshi, H. Yoguchi, T. Murakami, M. Jimbo, H. Nakamura and S.
Matsuura
|
| F03B/3 |
Application
of simplified buckling analysis rules of RCC-MR (1993) for PFBR-IHX
R. Srinivasan, S.P. Damodaran, P. Chellapandi, S.C. Chetal and S.B. Bhoje |
| F03B/4 |
Dynamic buckling
of thin cylindrical shells under shear loading
G. Michel, J.F. Jullien, A. Limam, N. Waeckel, A. Turbat and I. Politopoulos
|
| F04/1 |
A review
of simplified methods for the ratchetting assessment
L. Taleb, M. Cousin, J.F. Jullien and N. Waeckel |
| F04/2 |
The
ratchetting evaluation methods in Japanese demonstration FBR design
H. Wada, T. Otani and T. Fujioka |
| F04/4 |
Last improvements
on the ratchetting interaction diagram method
B. Riou, A.R.S. Ponter, K.F. Carter and J. Guinovart
|
| F04/5 |
Experiment and
numerical analysis of a typical nuclear piping submitted to large cyclic
thermal shocks
P. Geyer
|
| F04/6 |
Thermal
ratcheting in biaxial stress state. Effect of primary overloads
M. Rakotovelo, M. Cousin, L. Taleb and N. Waeckel |
| F05/1 |
Ratchetting
response of pipes and elbows under cyclic displacement controlled loads
T. Igari, H. Kaguchi, T. Fujioka, M. Jimbo and H. Morita |
| F05/2 |
Elastic
follow-up evaluation in pipes and elbows under displacement controlled loads
at elevated temperature
J. Orita, K. Nakamura, Y. Kamishima, T. Fujioka and H. Morita |
| F05/5 |
Validation
of the shakedown route in R5 for the assessment of creep fatigue crack initiation
P. Booth, P.J. Budden, I. Bretherton, S.K. Bate and Holdsworth |
| F06/1 |
Recent
developments in support to rules for welded joints: fatigue analysis
L. Le Ber, C. Sainte Catherine, F. Touboul, N. Waeckel and A. Turbat |
| F06/2 |
Structural
analysis of weldments in 316L (N) steels
S.K. Bate, I. Bretherton, F. Touboul, C. COudeville, C. Caroli, A. Miliozzi,
L. Sipione and D. Nicolini |
| F06/3 |
Feature
tests in support to rules for creep-fatigue analysis in welded joints
M.N. Berton, M. Guis, N. Waeckel and M. Turbat |
| F06/4 |
A contribution
to improvement of design rules on thermal striping
Y. Lejeail, M.T. Cabrillat, C. Poette and C. Mallez |
| F06/5 |
Application of
viscoplastic theory to high temperature design of fast breeder reactor
components
P. Chellapandi, S.C. Chetal and S.B. Bhoje
|
| F06/6 |
Experimental simulation
of creep fatigue damage in the PFBR control plug mock-up
P. Chellapandi, G. Thomas, S.C. Chetal and S.B. Bhoje
|
| F07/1 |
Strength of short-radius
thin-walled pipe elbows under in-plane bending loads
K. Nakamura, H. Wada, H. Nakamura and S.I. Matsuura
|
| F07/2 |
Simplified modelling
of pipe bend connection subjected to cyclic loading
Z.B. Petkov, M.J. Jordanov and Hr. Dochev
|
| F07/3 |
A simplified design
method of piping subjected to thermal loads at elevated temperature
H. Kaguchi, H. Wada, J. Orita, T. Fujioka, M. Jimbo and H. Morita
|
| F07/4 |
The advanced strength
assessment of WWER equipment and piping
S. Vejovoda
|
| F07/5 |
Modified solution
of radial nozzle with thick reinforcement in spherical vessel head subjected
to moment
Y.S. Sohn, Y.S. Lee and T.W. Kim
|
| F08/1 |
Assessment of failure
for fretting-wear of steam generator U-tubes
I.K. Kim
|
| F08/2 |
Optimization of
the contact area for the evaluation of bolted member stiffness
T.W. Kim, K.S. Kim and K.B. Park
|
| F08/3 |
Large diameter
studbolt with sleeve for reactor vessel or steam generator
B.W. Wedellsborg
|
| F09/3 |
Corrosion and mechanical
strength of RPV materials for BWR and PWR
V.A. Fedorova and B.T. Timofeev
|
| F09/4 |
Some problems VVER
Pressure Vessel brittle fracture in the regimes of maximum design emergency
B.T. Timofeev, V.V. Anikovsky and G.P. Karzov
|
| F09/5 |
System of rules
for WWER reactor pressure vessel lifetime assessment
M. Brumovsky and J. Zdarek
|
| FW/2 |
Discussion of the
rules to be applied for the leak before break analysis of the primary
loop piping
R. Gerard, C. Malekian and O. Meessen
|
| FW/3 |
RCC-MR code: presentation
emphasising recent design improvements
M. Sperandio, C. Escaravage, B. Drubay, D. Moulin, B. Salles and N.
Waeckel
|
| FW/4 |
An adaptation and
limit analysis method in the design of inelastic structures
G. Bielawski, A. Siemaszko and J. Zwolinskis
|
| FW/5 |
European
comparison of fast fracture analysis rules. Application of PWR reactor pressure
vessel case
J.M. Grandemange, D. Guichard, E. Keim, A. Shopper, D.G. Hooton, C.C.
France and J.K. Scharples |
| FW/6 |
Defect tolerance
under level D loading
D.G. Hooton
|
| FW/8 |
Improved design-by-analysis
procedures for LWR design codes
N.G. Smith, J.M. Grandemange, H. Hubel, M. Orsini and K. Schramm
|
| FW/9 |
Structural integrity
analysis and site measurement for the RPV of QINSHAN NPP
J. Qu, Y. Dou, Y. He, X. Shen, P. Wang and S. Xie
|
| FW/10 |
Primary, secondary
and peak stress indices for trunnion pipe support
D.H. Lee, J.M. Kim and S.H. Park
|
