| C01/1 |
INTERPIN.DF
modeling of secondary hydriding in Studsvik LWR fuel tests
C. Graslund, N. Kjaer-Pedersen and G. Lysell |
| C01/2 |
Modelling
of reactor fuel oxidation in steam atmosphere
B.Y. Dobrov, V.V.Likhanskii, VD Ozrin, A.A. Solodov, M.P. Kissane and
H. Manenc |
| C01/3 |
Rope
II. SKIROD and TOODEE2 calculations
K. Malén |
| C01/4 |
Framatome
creep fatigue-damage modelling on irradiated fuel cladding and its use for
fuel design
J. Joseph |
| C01/5 |
Mechanical
behaviour of high-bumup fuel during an RIA
C. Bernaudat and D. Paulsson |
| C01/7 |
Sensitivity
analysis applied to nuclear fuel performance related to fabrication parameters
and experiments
A.C. Marino and E.J. Savino |
| C01/8 |
Calculational
basis for WWER fuel rods safety
A.A. Tutiflov, A.A. Tutnov and A.I. Ulyanov |
| C02/1 |
A novel
fracture toughness testing method for irradiated tubing - Experimental results
and 3D numerical evaluation
V. Grigoriev, B. Josefsson, B. Rosborg and J. Bai |
| C02/2 |
Low
cycle corrosion fatigue of zircaloy-4 in iodine environment
J. Stolarz, A. Beloucif, T. Magnin and J. Joseph |
| C02/4 |
Impact
of fuel pellet fragmentation on pellet-cladding interaction in a PWR fuel
rods : results of the RECOR experimental programme
L. Caillot, G. Delette, B. Mien and J.C. Couty |
| C02/6 |
Development
of fuel rod welding for the Laguna Verde prototype fuel
C.A. Nocetti, J. Torres and F. Mercado |
| C03/1 |
Mechanics
of control element during irradiation
A.R. Massih, P. Isaksson and P. Stable |
| C03/3 |
Flow
characteristics for spacer grid with mixing vane of PWR fuel assembly
H.T. Lim, K.L. Jeon, J.H. Choi and B.S. Park |
| C03/4 |
Development
of a methodology for in-reactor fuel rod supporting condition prediction
H.K. Kim and K.T. Kim |
| C03/5 |
Design
optimization of PWR fuel rod plenum spring with equal or unequal extended
pitch
K.L. Jeon and J.H. Choi |
| C03/6 |
Structural
analysis of the graphite moderator cores within advanced gas cooled reactors
K.F. Carter |
| C03/7 |
Structural
assessment of 19 pin fuel bundle during refuelling
D.S. Chawla and H.S. Kushwaha |
| C04/1 |
Analytical
approach to PWR fuel assembly distortions
H. Salaun, J.P. Baleon and E. Francillon |
| C04/3 |
Developing
of FBR core irradiation-induced bowing analysis code RAINBOW
K. Itoh and T. Ohya |
| C04/4 |
Fretting
wear of fuel rods due to flow-induced vibration
Y.H. Kim, S.Y. Jeon and J.W. Kim |
| C04/5 |
Qualification
testing of PWR fuel assemblies at ABB
K.H. Haslinger, P.E, Joffre, F.V. Rossano F.V, S. Nilsson S. and L. Norstrom |
| C05K/1 |
Main
features and results of the IAEA coordinated research program on intercomparison
ofLMFR seismic analysis codes
M. Morishita, A. Rinejski, B. Fontaine, T. Horiuchi, K. Itoh, T. Kobayashi,
A. Martelli, R. Ravi, V.M. Silaev and K.K. Vaze |
| C05K/2 |
Intercomparison
of LMFBR seismic analysis codes -CEA contribution
B. Fontaine |
| C05K/3 |
Seismic
analysis of LMFBR cores
B. Murali, K.K. Vaze and H.S. Kushwaha |
| C05K/4 |
Analysis
of FBR-core seismic experiments using the SAFA program
T. Horiuchi, M. Nakagawa and T. Motomiya |
| C05K/5 |
Evaluation
of LMFBR core seismic analysis - Code verification and design consideration
T. Kobayashi |
| C06K/1 |
Seismic
response analysis of FBR core by FINAS code
M. Morishita |
| C06K/2 |
Verification
and validation analyses on LFMBR core mockup seismic experiments by FINDS
methods
K. Itoh, T. Ohya, and T. Satoh |
| C06K/3 |
Seismic
analysis of LMFBR cores-Symphony mock-up
B. Fontaine, T. Morin, M. Morishita and T. Asayama |
| C06K/5 |
Dynamic
response of PFBR core subassemblies under seismic excitation
R. Muralikrishna, P. Chellapandi, S.C. Chetal and S.B. Bhoje |
| C06K/6 |
The
effect of seismic level increase on fuel assembly response
M.-J. Jhung, J.B. Lee, Y.G. Yune and J.H. Lee |
| CW/1 |
Water
reactor fuel damage mechanisms: A review
C. Lemaignan |
| CW/2 |
SIERRA:
A code to predict the mechanical behavior of LWR fuel rods
M.R. Billaux, S.H. Shann, L.E. Van Swam, F. Sontheimer and H. Landskron |
| CW/3 |
Modelling
the steady state and transient mechanical behaviour of fuel rods
P. Garcia and M. Moyne |
| CW/4 |
Nonlinear
finite element studies of the pellet-cladding mechanical interaction in
a PWR fuel
J. Brochard, F. Bentejac and N. Hourdequin |
| CW/5 |
Modelling
of the fuel mechanical behavior : from creep laws to internal variable models
S. Leclercq |
| CW/6 |
A continuum
model for the mechanical behaviour of U02 fuel under cracking, relocation
and PCMI
L.O. Jernkvist |
| CW/7 |
Power
ramp and reshuffling analysis for nuclear fuels using the BACO code
A.C. Marino and E.J. Savino |
