Programme

Poster Gallery
(Posters will be on display throughout the entire conference)

All day

Track 2
Fuel development & fabrication

• DEVELOPMENT OF LEU SILICIDE FUEL ELEMENT FOR THE IPEN RESEARCH REACTOR
  H.G. Riella (IPEN) – Brazil

• DEVELPMENT OF LEU METALLIC URANIUM FABRICATION FOR RESEARCH REACTOR FUEL ELEMENT
  A. M. Saliba-Silva et al. (Instituto de Pesquisas Energéticas e Nucleares – Universidade Federal de Santa Catarina) – Brazil

• DIFFERENT APPROACHES FOR STUDYING TI EFFECTS ON UMO/AI SYSTEM
  M. Rodier et al. (CEA) – France

• RESULTS OF PRE-REACTOR EXAMINATION OF THE U-9MO-UO2-AI FUEL ELEMENTS FABRICATED BY THE EXTRUSION METHOD
  V. V. Popov et al. ( IPPE) – Russia

• RADIATION EFFECT ON MICROSTRUCTURAL STABILITY OF RERTR FUEL
  J. Gan et al. (INL – University of Wisconsin) – USA

• THERMAL AND CHEMICAL STABILITY OF SOME HYPOEUTEIODES y-UMo ALLOYS
  F. Branco Vaz de Oliveira et al. (IPEN – Federal University of Santa Catarina) – Brazil

• DISTINCTIVE FEATURES OF INTERACTION OF THE U-MO FUEL COMPOSITION FISSION PRODUCTS AND THE AI MATRIX WITH BARRIER COATING
  D. Shornikov (Moscow Engineering Physics Institute) – Russia

• PROGRESS IN HEAVY ION BOMBARDEMENT OF U-MO/AI DISPERSION FUEL
  J. Jungwirth et al. (Technical University of Munich – MLL – University of the German Bundeswehr) – Germany

• MANUFACTURING OF THICK MONOLITHIC LAYERS BY DC-MAGNETRON SPUTTERING
  W. Schmid et al. (MLL – Technical University of Munich) - Germany

• THE EFFECT OF FUEL BURN-UP FOLLOWED BY ANNEALING ON CHANGES IN STRUCTURE AND STRUCTURAL PARAMETERS OF U-9% Mo DISPERSION FUEL
  A. Golosov (Institute for Nuclear Materials) – Russia

All day

Track 3
Reactor operation, fuel safety and core conversion

• ZIRCALLOY EFFECT ON THE LEU FUEL ENRICHMENT OF THE SYRIAN MNSR
  M. Albarhoum (Atomic Energy Commission) – Damascus-Syria

• STUDY OF AI FUEL PLATE OXIDATION
  R. Haddad et al. (CNEA) – Argentina

• STUDY OF NUCLEAR FUEL BURN-UP IN A LOW POWER REACTOR
  L. Heraltová and A. Kolros (Faclty of Nuclear Sciences and Physical Engineering) – Czech Republic

• MODELLING OF NUCLEAR BEHAVIOUR IN RESEARCH REACTORS
  T. Totev and P. Lemoine (ANL – CEA) – USA/France

• RESULTS OF THE REACTOR CONTROL SYSTEM REPLACEMENT AND REACTOR CORE CONVERSION AT THE DALAT NUCLEAR RESEARCH REACTOR
  Pham Van Lam (Nuclear Research Institute Dalat) – Vietnam

All day

Track 4
Fuel back-end management

• SPENT FUEL ASSEMBLIES MANAGEMENT AT IEA-R1 RESEARCH REACTOR
  R. Frajndlich (IPEN) – Brazil

• TOPICS ON GAMMA-RAY CONTROL OF THE COMPOUND METAL AND CONCRETE PROTECTION QUALITY ( NUCLEAR FUEL TRANSPORTING CASK)
  N. Shchigolev (SPb Nuclear Physics Institute RAS) – Russia

• RESEARCH REACTOR DAMAGED SPENT FUEL MANAGEMENT
  O. Barinkov et al. (R&D Company SOSNY) – Russia

• PREPARATION AND ORGANISATION EXPERIENCE OF SFA TRANSPORTATION FROM LVR-15 RESEARCH REACTOR (NRI, REZ, CZECH REPUBLIC) TO THE RUSSIAN FEDERATION
  A. Dorofeev et al. (R&D Company SOSNY) – Russia

• ŠKODA TRANSPORT AND STORAGE SYSTEM UTILIZING THE ŠKODA VPVR/M CASK
  M. Picek and P. Ružicka (Škoda JS a.s.) – Czech Republic

• PROGRESS IN THE SHIPPING ACTIVITIES OF THE SPENT NUCLEAR FUEL FROM IRT-2000 FACILITY, SOFIA, BULGARIA
  T. Apostolov et al. (Institute for Nuclear Research and Nuclear Energy of Bulgarian Academy of Science) – Bulgaria

• ADOPTION OF THE BUDAPEST RESEARCH REACTOR FACILITY FOR SNF SHIPMENT
  J. N. Dewes and S. Tózsér (Washington Savannah River Co – Atomic Energy Research Institute) – USA/Hungary

All day

Track 5
Innovative methods in research reactor analysis

• CALCULATION OF NEUTRON FLUX TRANSIENTS
  F. Reisch (KTH, Royal Institute of Technology) – Sweden

• USING MONTE CARLO INSTRUMENTATION CODES FOR THE OPTIMISATION OF HIGH FLUX RESEARCH REACTORS
  M. Englert and W. Liebert ( IANUS-University of Darmstadt) – Germany