Actinide and Fission Product Partitioning and Transmutation

12th Information Exchange Meeting

Prague, Czech Republic | 24-27 September 2012

Home | Programme | Presentations | Poster sessions (abstract & full paper when available)


Poster sessions

Session I: International and National programmes

  • SCENARIOS FOR FAST REACTOR DEPLOYMENT WITH PLUTONIUM RECYCLING
    Coquelet Abstract
  • Advanced Fuel Cycle Simulator Description
    Dixon Abstract
  • IMPORTANCE OF THE SCENARIO STUDIES ON THE "BY DESIGN" PROLIFERATION RESISTANCE IMPROVEMENT
    Glinatsis Abstract | Full paper
  • TRANSITION FROM THERMAL TO FAST REACTORS IN FINLAND
    Juutilainen Abstract | Full paper
  • ANALYSIS OF A FAST REACTOR TRANSITION SCENARIO WITH EVOLCODE/TR_EVOL
    Merino Rodríguez Abstract | Full paper
  • FUEL CYCLE STUDIES ON MINOR ACTINIDE BURNING IN GAS COOLED FAST REACTORS
    Szieberth Abstract | Full paper
  • PREVENTIVE WAY OF RELATIVELY LOW RADIACTIVE WASTE ENERGY PRODUCTION BY THORIUM-URANIUM FUEL CYCLE APPLICATION
    Szuta Abstract | Full paper
  • ACTINIDE AND FISSION PRODUCT EVOLUTION BENCHMARKING WITH VANDELLOS II (PWR-SPAIN) MEASURED ISOTOPIC VALUES WITH CONSIDERING ALL THE BURN-UP HISTORY WITH CONSECUTIVE CALCULATION
    Töre Abstract

Session II: Fuel cycle strategies and transition scenarios

  • SEPARATION OF GROUP I AND II FISSION PRODUCTS FROM LiCl WASTE SALTS DELIVED ELECTROLYTIC REDUCTION PROCESS OF USED OXIDE FUEL
    Cho Abstract
  • One-Group Fission Cross Sections for Plutonium and Minor Actinides Inserted in Calculated Neutron Spectra of Fast Reactor Cooled with Lead-208 or Lead-Bismuth Eutectic
    Khorasanov Abstract | Full paper
  • DECONTAMINATION OF SPENT DIAMEX SOLVENTS CONTAINING CONTAMINANTS DIFFICULT TO STRIP
    Mares Abstract
  • A NEW METHOD FOR STABILIZATION/SOLIDIFICATION OF RADIOACTIVE WASTE SALT (LiCl, LiCl-KCl) FROM PYROCHEMICAL PROCESS
    Park Abstract | Abstract

Session III: Impact of P&T on geological disposal 

  • The use of GFR dedicated assemblies in the frame of advanced symbiotic fuel cycles: an innovative way to minimize the long-term spent fuel radiotoxicity
    Cerullo Abstract | Full paper
  • MINOR ACTINIDE TRANSMUTATION IN A GAS-COOLED FAST REACTOR
    Perkó Abstract | Full paper
  • Molten Salt Fast Reactor (MSFR) based on LiF-NaF-KF
    Ponomarev Abstract

Session IV: Transm. Syst.: design, perform. and safety

Session V: Pyro and aqueous separation processes

  • Investigation of metal ion extraction and aggregate formation combining acidic and neutral organophosphorous reagents
    Braatz Abstract
  • AQUEOUS COMPLEXATION AND INTERACTIONS OF ND(III) AND AM(III) WITH CITRATE IN PERCHLORATE MEDIA
    Brown Abstract
  • A N,N´-di-n-OKTYL-TODGA-dicarbollide Extractant for Actinide(III) Separation from Acidic Waste Solutions
    Bubeníková Abstract | Full paper
  • A kinetic study on the extraction of Americium(III) into CyMe4-BTBP
    Geist Abstract | Full paper
  • EXPLORATION OF A NOVEL SOFT DONOR EXTRACTANT FOR PRECIOUS METAL RECOVERY IN SPENT NUCLEAR FUEL AND ELECTRONIC WASTE REPROCESSING
    Gullekson Abstract
  • Removal of Uranium from Thorium-Uranium SIMFUEL by Fluoride Volatility
    Hamilton Abstract | Full paper
  • A FEASIBILITY STUDY ON IODINE BEHAVIOR DURING PYROPROCESSING OF SPENT METALLIC FUEL
    Kim Abstract | Full paper
  • SIMULATOR OF THE BEHAVIOR OF CURIUM COMPOUNDS IN NaCl-2CsCl EUTECTIC
    Kormilitsyn Abstract
  • Removal of Adhered Salt from Uranium Deposits in Pyroprocess
    Kwon Abstract | Full paper
  • Development of an integrated sieve-crucible assembly for the sequential operation of a liquid salt separation and a distillation
    Kwon2 Abstract | Full paper
  • IDENTIFICATION OF N,N`-DIETHYL-N,N`-DITOYLDIPICOLINAMIDE DEGRADATION PRODUCTS BY GAS CHROMATOGRAPHY-MASS SPECTROSCOPY
    Lapka Abstract
  • LOADING AND FLOW-RATE DEPENDENCE OF THE TRANSFER RATES IN A CENTRIFUGAL CONTACTOR USING ORGANIC LIGAND CYME4-BTBP
    Magnusson Abstract | Full paper
  • TECHNOLOGICAL VERIFICATION OF FLUORIDE VOLATILITY METHOD
    Marecek Abstract | Full paper
  • DETERMINING THE THERMODYNAMICS OF EXTRACTION OF AMERICIUM AND CURIUM BY HDEHP FROM NITRATE SOLUTION
    Martin Abstract
  • SELECTIVE UPTAKE OF CESIUM BY HYBRID ADSORBENTS ENCLOSING HETEROPOLYACID
    Mimura Abstract | Full paper
  • ELECTROCHEMICAL AND THERMODYNAMIC PROPERTIES OF NEODIMIUM IN MOLTEN CHLORIDES
    Novoselova Abstract | Full paper
  • ELECTROCHEMICAL AND THERMODYNAMIC PROPERTIES OF THULIUM IN MOLTEN CHLORIDES
    Novoselova Abstract | Full paper
  • STRUCTUREAL STUDIES ON EXTRACTED SPEICES BY USING DIAMIDE COMPOUNDS AS EXTRACTANT FOR ACTINIDE/LANTHANIDE SEPARATION
    Okumura Abstract | Full paper
  • BENCHMARK ON CU-NI CO-DEPOSITION IN CUSO4/NISO4 SOLUTION BY THREE-DIMENSIONAL MASS TRANSPORT AND ELECTROCHEMICAL MODEL
    Park J Abstract | Full paper
  • Purification of Used Zr Scrap by Molten Salt Electrorefining
    Park KT Abstract
  • CONFIGURATION MANAGEMENT OF DESIGN REQUIREMENTS FOR NUCLEAR FUEL CYCLE FACILITY
    Park HS Abstract | Full paper
  • REDOX REACTIONS OF NEPTUNIUM WITH NITROUS ACID AND ACETOHYDROXAMIC ACID UNDER RADIOLYSIS CONDITIONS
    Precek Abstract
  • OPTIMIZATION OF THE EXTRACTION OF 137Cs AND 90Sr FROM HIGH LEVEL LIQUID WASTE
    Rais Abstract | Full paper
  • Minor actinide partitioning: main outcomes in the framework of the 2006 French act
    Rostaing Abstract
  • Thermodynamic properties of heterogeneous alloys of lanthanum with gallium-indium eutectic
    Schetinskii Abstract
  • Electrochemistry of selected lanthanides in LiF-BeF2 system
    Straka Abstract | Full paper
  • SEPARATION OF MINOR ACTINIDES AND FISSION PRODUCTS BY USING SOLID EXTRACTANTS
    Suzuki Abstract
  • PULSE ELECTROLYSIS OF URANIUM IN MOLTEN FLUORIDE SALTS
    Szatmáry Abstract | Full papaer
  • ALTERNATIVE PYROCHEMICAL REPROCESSING OF USED NUCLEAR FUEL USING MOLYBDATE MELTS
    Tkac Abstract
  • Kinetics back-extraction of Tc (VII) by DFG from 30% TBP solution using Lewis cell
    Vidanov Abstract
  • ALPHA-RAY IRRADIATION ON ADSORBENTS OF EXTRACTION CHROMATOGRAPHY FOR MINOR ACTINIDE RECOVERY
    Watanabe Abstract | Abstract

Session VI: Transmutation fuels and targets

  • CURRENT STATUS AND FUTURE DEVELOPMENTS OF THE TRANSURANUS CODE: OXIDE FUELS FOR MINOR ACTINIDES RECYCLING
    Calabrese Abstract | Full paper
  • IRRADIATION PERFORMANCE COMPARISON OF EXPERIMENTAL AND PROTOTYPIC LENGTH METALLIC (U-10ZR) FUEL
    Carmack Abstract
  • Investigation of pelletized and sphere-packed oxide fuels for Minor Actinide transmutation in Sodium Fast Reactors, within the FP-7 European project PELGRIMM
    Delage Abstract | Full paper
  • RADIAL PROFILE OF THERMAL DIFFUSIVITY AT HIGH SPATIAL RESOLUTION ON METALLIC TRANSMUTATION FUELS
    Kennedy Abstract

Session VII: Transm. physics, experim. and nuclear data

  • SENSITIVITY/UNCERTAINTY ANALYSIS OF THE VALIDATION OF THE EVOLCODE 2.0 BURN-UP SYSTEM WITH PWR EXPERIMENTAL DATA
    Alvarez-Velarde Abstract | Full paper
  • Thermal Hydraulic Study of Natural convection in the Heavy Eutectic liquid metal Loop HELIOS, Benchmark RESULTS on Lead-Alloy Cooled Advanced Nuclear Energy System (LACANES)
    Batta Abstract | Full paper
  • Accurate Nuclear data for present and future reactors from the ANDES project
    González Abstract
  • Perspective of the Accelerator-Driven System with High-Energy Protons in the Kyoto University Critical Assembly
    Pyeon Abstract
  • INTELLIGENT NUCLIDE SELECTION CAPABILITY IN THE REACTOR PHYSICS AND INVENTORY CALCULATION CODE SERPENT
    Viitanen Abstract | Full paper

Last reviewed: 28 June 2013