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

TECHNICAL 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