08.30 - 08.35

Announcement: Presentation of the Research Reactor Safety Section of the IAEA (204kb)

H. Abou Yehia - IAEA

08.35 - 09.00

Progress in conversion from HEU to LEU fuel at IRT-200, Sofia (532kb)

T. Apostolov, S.I. Belousov - INRNE, Bulgaria; N. Hanan, J.E. Matos - ANL, USA

09.00 - 09.25

Reduced enrichment program for FRM II, actual status & a principal study of monolithic fuel for FRM II (806kb)

A. Röhrmoser, W. Petry - Munich TU, Germany

09.25 - 09.50

HTGR Coated Fuel Particles as Fuel for High Flux Water-Cooled Research Reactors (313kb)

V.A. Tsykanov, A.V. Klinov, V.A. Starkov, V.Ye. Fedoseyev, N.G. Gataullin, V.V. Pimenov – RIAR, Russia

09.50 - 10.15

HEU / LEU conversion of the Petten HFR

P.J.M. Thijssen – NRG, The Netherlands

10.45 - 11.10

HOR HEU / LEU core conversion: 8 years of experience (984kb)

J.W. de Vries, P.F.A. de Leege, H.P.M. Gib-cus – Delft TU, Netherlands

11.10 - 11.35

Consideration of experimental data from an instrumented fuel element in the evaluation of the safety of IRIS experiments in the OSIRIS reactor (1,523kb)

N. Fournier, L. Bertrand, J. Couturier – IRSN, France

11.35 - 12.00

Irradiation qualification of a Chilean test fuel element (1,832kb)

P.J.M. Thijssen, F.J. Wijtsma, R.H.J. Schur-ing, K. Bakker – NRG, Netherlands; J. Marin, J. Lisboa, L. Olivares – CCHEN, Chile

08.30 - 08.55

A sophisticated Monte-Carlo-code system for the safety and core physics analysis of FRJ-2 (719kb)

R. Nabbi, G. Damm - Jülich Research Centre, Germany

08.55 - 09.45

3-D fuel modeling with MCNP & ORIGEN-S
&
Simulation of irradiation history in combined annular multi-tube fuel element of BR2 (1,658kb)

S. Kalcheva, E. Koonen - SCK-CEN, Belgium
&
V. Kuzimov, E. Koonen - SCK-CEN, Belgium

09.45 - 10.10

Safety study on reactive properties of foreseen BR2 fuel elements containing Cadmium wires instead of burnable poisons (658kb)

A. Beeckmans de West-Meerbeeck - SCK-CEN, Belgium

10.40 - 11.05

Development of a fuel burn-up calculation model in a reduced reactor geometry (252kb)

T. Sembiring - BATAN, Indonesia; P.H. Liem, Tokyo Institute of Technology, Japan

11.05 - 11.30

Application of best estimate thermal-hydraulic codes for the safety analysis of research reactors (454kb)

M. Adorni, A. Bousbia-Salah, F. D´Auria - Pisa University, Italy; Nabbi, R. - Jülich Research Centre, Germany

11.30 - 11.55

Configuration and thermal hydraulic calcu-lations of reactor core IRT-200 with low en-riched fuel IRT-4M (373kb)

T. Apostolov, S. Kadalev INRNE, Bulgaria; P. Egorenkov Kurchatov Institute, Russia;
A. Olson ANL, USA

11.55 - 12.20

Power upgrading of the Teheran research reactor (1,299kb)

M. Gharib - Nuclear Research Centre, Atomic Energy Organization of Iran, Iran