ICN - Pitesti

RADIOACTIVE WASTE AND SPENT NUCLEAR FUEL MANAGEMENT

Main research areas:

  • Radioactive waste characterisation: development of methods for the characterisation of radioactive waste generated from the operation, maintenance and decommissioning of Cernavoda NPP, those generated from INR nuclear installations and from other applications of nuclear techniques;
  • Development of new technologies for treatment/conditioning of various types of radioactive waste (liquid aqueous waste, sludge, magnetite, irradiated graphite ) arising from the operation, maintenance and decommissioning of Cernavoda NPP, those generated from INR activities or from other applications of nuclear techniques;
  • Development of (experimental and modeling) methodologies necessary to support the safe storage and disposal program of low and medium active radioactive waste;
  • Development of (experimental and modeling) methodologies necessary to support the safe storage and disposal program of long life radioactive waste and of CANDU spent fuel.

Main research results:

  • Small scale mobile installation for decontamination of aqueous liquid radioactive waste by ionic exchange;
  • Mineralization methods by microwave digestion for different radioactive waste and environmental matrices (i.e. paper, plastics, charcoal, ion exchange resins, graphite, oil, concrete, soil);
  • Analytical method and experimental set-up for inorganic and organic C-14 quantification in aqueous solutions, spent ion exchange resins, irradiated graphite and irradiated Zy-4;
  • Separation and purification method for alpha emitting radionuclides, for their measurement by alpha spectrometry;
  • Technical solutions to be applied at Cernavoda NPP for optimization of the installation for liquid aqueous radioactive waste decontamination;
  • Method and technological flow sheet for treatment and conditioning the spent molecular sieve;
  • Method and technological flow sheet for treatment the radioactive sludge in microwave field;
  • Pilot facility for treatment the liquid radioactive waste, aqueous radioactive waste, by reverse osmosis;
  • Radiologic characterisation of TRIGA irradiated graphite ;
  • Experimental gas migration through compacted bentonite;
  • Database containing the main hydrogeological characteristics of Saligny site and transport parameters (diffusion and distribution coefficients) for the main radionuclides through engineered (concrete and improved loess) and natural barriers (clay, loess, limestone) of the Saligny disposal system;
  • Performance and safety assessment for Saligny disposal system;
  • Preoperational monitoring program of Saligny site;
  • Separation and purification methods for difficult to measure radionuclides (I-129, Tc-99, Ni-63 si Sr-90), for their measurement by liquid scintillation spectrometry (LSC);
  • Methods for C-14 and H-3 quantification from different radioactive waste by combustion in oxygen rich atmosphere and activity measurement through spectrometry with liquid scintillations;
  • Scientific books published on the radioactive waste management field ;
  • Scientific articles presented in national and international conferences and published in scientific journals.

Contact: Dr. fiz. Crina BUCUR; e-mail: crina.bucur@nuclear.ro

Last modified: 18-02-2019.


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