Programme

Tuesday 04 March 2008

08.30 - 10.30

Session II – Part 3
Fuel development & fabrication

Chairmen: M. Ripert (CEA/DEC) and D. Wachs (INL)

• MICROSTRUCTURAL ANALYSIS OF IRRADIATED ATOMIZED U(MO) DISPERSION FUEL IN AN AI MATRIX WITH SI ADDITION
  A. Leenaers et al. (SCK-CEN – CEA) – Belgium/France

• ABOUT THE EFFECTS OF SILICON AND/OR TITANIUM ADDITIONS ON THE UMO/AL INTERACTIONS
  X. Iltis et al. (CEA) – France

• UPDATE ON MECHANICAL ANALYSIS OF MONOLITHIC FUEL PLATES
  D. E. Burkes (Idaho National Laboratory) – USA

• MONOLITHIC UMO PLATES WITH ZIRCALOY CLADDING
  E. E. Pasqualini (CNEA) – Argentina

• CHARACTERISATION OF U-MO FISSION GAS BUBBLES ON GRAIN BOUNDARIES
  J. Rest (Argonne National Laboratory) – USA

• NEW SILICIDE FUEL PLATE DEVELOPMENTS AT AREVA-CERCA
  I. Caillière et al. (AREVA-Cerca) – France

10.30 - 11.00

Coffee Break

11.00 - 11.40

Session II – Part 4
Fuel development & fabrication

Chairmen: M. Ripert (CEA/DEC) and D. Wachs (INL)

• STUDY OF THE CORROSION OF AN ALUMINIUM ALLOY USED FOR THE FUEL CLADDING OF THE JULES HOROWITZ MATERIAL TESTING REACTOR: OXIDE MICROSTRUCTURE AND IRRADIATION EFFECTS
  M. Wintergerst et al. (CEA – Institut de Physique Nucléaire) – France

• AREVA-CERCA TEN YEARS LICENSE FOR FUEL FABRICATION
  T. Pin and E. Torlini (AREVA-Cerca) – France

11:40 - 12:40

Session III – Part 1
Reactor operation, fuel safety and core conversion

Chairman: J.G. Marques (Instituto Tecnológico e Nuclear)

• THE CONVERSION PROGRAMME: AUTHORITIES, ACTIVITIES AND PLANS FOR THE MININIZATION OF HIGH ENRICHED URANIUM THROUGH THE GLOBAL THREAT REDUCTION INITIATIVE
  P. Staples and N. Butler (National Nuclear Security Administration) – USA

• COMMISSIONING OF THE NEW LEU CORE OF THE PORTUGUES RESEARCH REACTOR
  J. G. Marques et al. (Instituto Tecnológico e Nuclear – ANL) – Portugal/USA

• LESSONS LEARNED FROM U.S. DOMESTIC REACTOR CONVERSION PROGRAMME
  E. C. Woolstenhulme and D. Meyer (INL) – USA

12.40 - 14.00

Lunch Break

14.00 - 15.40

Session III – Part 2
Reactor operation, fuel safety and core conversion

Chairman: A.M.A. Shokr (IAEA)

• SAFETY ASPECTS OF RESEARCH REACTOR CORE FUEL CONVERSION FROM HIGHLY ENRICHED URANIUM TO LOW ENRICHED URANIUM
  A. M. A. Shokr and H. A. Yehia (IAEA) – Austria

• IMPACT ON FUEL CYCLE COSTS OF CONVERSION TO LOW ENRICHED URANIUM FUELS
  K. Alldred and N. Mote ( International Nuclear Enterprise Group) – USA

• OPTIMIZATION STUDIES FOR CONVERSION OF THE MIT REACTOR TO LEU FUEL
  T. H. Newton et al. (MIT – ANL) – USA

• OPTIMIZED CONTROL ROD DESIGN OF THE RESEARCH REACTOR BR2
  S. Kalcheva and E. Koonen (SCK-CEN) – Belgium

• STEP REACTIVITY TRANSIENT THERMAL HYDRAULIC AND SAFETYANALYSES OF A PROPOSED HEU & LEU CORE FOR SAFARI-1 RESEARCH REACTOR
  A. Sekhri et al. (NECSA) – South Africa

15.40 - 16.20

Coffee break

16.20 - 18.00

Session III – Part 3
Reactor operation, fuel safety and core conversion

Chairman: W. Knop (GKSS)

• THE FIRST EUROPEAN FOCUSSING COLD NEUTRON SOURCE – OPERATIONAL EXPERIENCE AND NEUTRONICS RESULTS
  W. Knop and P. Schreiner et al. (GKSS) – Germany

• THE ENERGY RELEASE AND FUEL BURN-UP DETERMINATION METHODS IN THE MIR REACTOR
  A. I. Izhutov et al. (Research Institute of Atomic Reactors) – Russia

• REACTOR UPGRADE OF AGN-201 in KHU, KOREA
  M.H. Kim (Kyung Hee University) – South Korea

• ANALYSIS OF THE CALCULATIONAL TECHNIQUES OF HEAT DEPOSITION VIA MCNP IN COMPARISON WITH A CALORIMETER EXPERIMENT AT SAFARI-1 RESEARCH REACTOR
  M. Belal and B. Makgopa (NECSA) – South Africa

• SAFETY ANALYSIS OF REACTIVITY INITIATED ACCIDENTS (RIA) AND
  ANTICIPATED TRANSIENTS WITHOUT SCRAM (ATWS) OF THE BUDAPEST
  RESEARCH REACTOR
  A. Keresztúri et al. (KFKI – Atomic Energy Research Institute) – Hungary

20:00 - 24:00

Conference dinner at traditional storage house in port district (Speicherstadt)