Wednesday 3 May 2006
Please note that sessions 4 and 5 will run IN PARALLEL

Session 4

Reactor operation, fuel safety, core conversion - Chair: T. van der Hagen - Delft Reactor Institute, Netherlands

08.30 - 08.35

Announcement: Presentation of the Research Reactor Safety Section of the IAEA

H. Abou Yehia - IAEA

08.35 - 09.00

Progress in conversion from HEU to LEU fuel at IRT-200, Sofia – invited paper

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

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

09.25 - 09.50

HTGR Coated Fuel Particles as Fuel for High Flux Water-Cooled Research Reactors

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

10.15 - 10.45

Coffee break and poster viewing

10.45 - 11.10

HOR HEU / LEU core conversion: 8 years of experience

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

11.10 - 11.35

Neutronics calculation in core conversion for DALAT nuclear research reactor from WWR-M2 HEU to WWR-M2 LEU

Nguyen Kien Cuong – Nuclear Research In-stitute, Vietnam

11.35 - 12.00

Consideration of experimental data from an instrumented fuel element in the evalu¬ation of the safety of IRIS experiments in the OSIRIS reactor

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

12.00 - 12.25

Irradiation qualification of a Chilean test fuel element

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

Session 5

Innovative methods in research reactor analysis Chair: Rahim Nabbi, Jülich Research Centre, Germany

8.30 - 8.55

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

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

8.55 - 9.20

3-D fuel modeling with MCNP & ORIGEN-S

S. Kalcheva, E. Koonen - SCK-CEN, Belgium

9.20 - 9.45

Simulation of irradiation history in combined annular multi-tube fuel element of BR2

V. Kuzimov, E. Koonen - SCK-CEN, Belgium

9.45 - 10.10

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

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

10.10 - 10.40

Coffee break and poster viewing

10.40 - 11.05

Development of a fuel burn-up calculation model in a reduced reactor geometry

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

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

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

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

12.20 - 12.45

Impact on core parameters due to Mo-99 target plates inclusion in SAFARI-1 core modelling

L.E. Moloko, R.H. Prinsloo, A.L. Graham - NECSA, South Africa

12.45 - 13.00

Summary and Closing Remarks
P. Gubel, Conference Chairman

13.00 - 14.00

Closing lunch