POSTER PRESENTATIONS
Posters will be on display
throughout the conference
|
Posters, session
2:
Fuel development, qualification, fabrication and licensing
|
Specific features of UMo fuel - Al matrix interaction
|
A.M. Savchenko, A.V. Vatulin, I.V. Dobrikova , Y.
Konovalov - Bochvar Institute, Russia
|
The development
of U-7Wt.%Mo for large particle powders by centrifugal atomization
|
S.J. Oh, K.H. Kim, S.J. Jang,
D.B. Lee, Y.S. Lee, J.M. Park, H.D. Park, C.K. Kim - KAERI,
Korea |
Corrosion
behavior of aluminium cladding fuels in HANARO core |
H.T. Chae, H. Kim, C. Park, J.M. Park,
C.K. Kim, B.J. Jun – KAERI, Korea
|
Out
and in pile diffusion experiments between U-Mo alloys and Al-Si
alloys: Work status |
M. Mirandou, A.M. Fortis,
S. Balart - CNEA, Argentina |
New methods for
measuring uranium superficial density in MTR fuel plates using
radiography |
F. G. Marlasca, M. Hey, J.
Fabro, M. Restelli - CNEA, Argentina |
Neutronic and
thermal-hydraulics calculation of U-Mo dispersion fuel for utilization
in the IEA-R1 reactor core |
A. T. Sila, C. T. Almeida,
P.E. Umbehaun, M. Yamaguchi, J.E.R. Silva, G. Lucki - IPEN,
Brazil |
Posters,
session 3:
Spent fuel management, back-end options, transportation
|
The long way
of the irradiated fuel elements of the Rossendorf research reactor
to an interim storage facility |
U. Helwig, W. Boeßert
- Nuclear Engineering & Analytics Rossendorf, Germany |
Mechanisms of
cladding corrosion during long term interim storage of MTF spent
nuclear fuel in water basins |
R. Haddad, L. Lanzani, S.
Rodríguez - CNEA, Argentina |
Spent nuclear
fuel storage and preparation of SNF shipment to Russia at NRI
Rez |
J. Rychecky, V. Broz - NRI,
Czech Republic |
Transport cask
fleet analysis for JHR reactor |
J. Dumesnil, D. Iracane, P.
Malvache CEA, France; F.C. Hugon, C. Chivrac, D. Ohayon COGEMA
Logistics, France |
A study on aluminium corrosion
in water using a rack with vertically and horizontally immersed
coupons in spent fuel storage pool |
M. Pešic, T. Maksin, R. Dobrijevic
- VINCA Institute, Serbia & Montenegro |
Options for the spent fuel
interim storage of the IEA-R1 research reactor in Brazil |
A. T. Sila, M. Mattar Neto, M.C. C. Silva
- IPEN, Brazil |
Criticality safety analysis
of IRT-200 storage pool with IRT-4M fuel assemblies |
M. Manolova, S. Kadalev - INRNE, Bulgaria |
Development of treatment technology
and self disposal method of uranium sludge |
N.G. Kim, C.H. Jung, W.Z. Oh - KAERI, Korea |
Posters,
session 4:
Reactor operation, fuel safety, core conversion
|
44 years of operation - The
successful fuel history of the TRIGA Mark II reactor in Vienna |
M. Villa, H. Böck, - Atominstitut,
Austria |
The new radiation monitoring
systems at the Nuclear Scientific and Experimental Reactor -
IRT 200 |
E. Moskov, T. Mishev, A. Mladenov - INRNE,
Bulgaria |
Optimization calculations
for the use of monolithic UMo fuel in high-flux research reactors |
M. Englert, W. Liebert - Darmstadt TU,
Germany; A. Glaser - Princeton University, USA |
Feasibility study of VVRK-reactor
conversion to low-enriched fuel |
F.M. Arinkin, Sh.Kh. Gizatulin, Zh. R.
Zhotabaev, K.K. Kadyrzhanov, S.N. Koltochnik, V.A. Nasonov,
P.V. Chakrov, L.V. Chekushina - Institute of Nuclear Physics,
Kazachstan |
The experimental activities
developed at IPEN for thermal-hydraulic analysis of the IEA-R1
research reactor |
P.E. Umbehaun, , W.M. Torres, J.E.R. Silva,
R. Frajndlich - IPEN, Brazil |
T
ECHNICAL TOURS (3 OPTIONS)
Busses will depart from the Kempinski
Hotel. Please take your passport with you.
|
Wednesday
3 May 2006 |
Sofia IRT-200
Research Reactor |
departure 14.30
return 17.00 |
Wednesday
3 May 2006 |
Novi Han Radwaste Repository |
departure 14.30
return 18.00 |
Thursday
4 May 2006 |
Kozloduy Nuclear Power Plant |
departure 8.00
return 18.00 |
