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