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 (molecular jiggers, slime) arising from the operation, maintenance and decommissioning of Cernavoda NPP, those generated from INR activities or from other applications of nuclear techniques;
- Design, development and testing of the spent fuel storage basket and of its transfer cask of at Intermediate Storage of Spent Fuel;
- 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;
- Long term behaviour of spent nuclear fuel in the Final Repository.
Main research results:
- Mobile installation achievement of small-scale for decontamination of small quantities of aqueous liquid radioactive waste and testing it using real waste coming from Cernavoda NPP;
- Design and testing of a passive collector for tritiated water for collecting Tritium samples as tritiated water vapors from the workplaces atmosphere from Cernavoda NPP;
- Reverse osmosis pilot facility for processing liquid radioactive waste, manufactured for selecting the optimal membrane materials and the optimal configuration of a nuclear-specific application.
- Characterisation of irradiated graphite from the thermal column of the TRIGA (in the framework of FP7 - CARBOWASTE project);
- Methods for chemical decontamination of irradiated graphite from the thermal column of the TRIGA (in the framework of FP7 - CARBOWASTE project);
- Experimental facility for the study of gas migration through compacted bentonite (in the framework of FP7 - FORGE project);
- Saligny site characterisation which was selected for the location of the final storage facility of low and medium active radioactive waste (DFDSMA) for the preliminary safety report of DFDSMA Saligny;
- Determination of the transport parameters for the main radionuclides from the low and medium active radioactive waste through engineering barriers (cement) and natural ones (loess, clays, chalkstone) of the Saligny storage system, for the preliminary safety report of DFDSMA Saligny;
- Performance assessment for the Saligny site;
- Development of the preoperational monitoring program of Saligny site (carried out within the PN II - MONA project);
- Development of separation methods for I-129, Tc-99 and Cl-36 from simulated aqueous radioactive waste for their subsequent measurement;
- Development of the C-14 determination methods from different radioactive waste: the samples' combustion and C-14 measurement through spectrometry with liquid scintillations;
- Publication of the specialty books;
- Papers presented at scientific events and published in scientific journals.
Contact: Dr. fiz. Crina BUCUR; e-mail: firstname.lastname@example.org