ICN - Pitesti

RADIOACTIVE WASTE TREATMENT AND CONDITIONING PLANT

The Radioactive Waste Treatment and Conditioning Plant ensures collecting, treating and conditioning of the radioactive waste resulted from the TRIGA reactors, the Nuclear Fuel Factory (FCN), Post-Irradiation Examination Laboratory (LEPI) and other nuclear installations within ICN and in the country, but also developing and implementing new equipment and technologies.

Conditioning facility through bituminization of spent ion resins

Activities

  • Characterizing and sorting radioactive waste;
  • Radioactive waste treatement and their conditioning in stable matrices ;
  • The transfer of conditioned radioactive waste to the National Radioactive Waste Repository Baita Bihor.

CNCAN licensed radiological installations for the treatment and conditioning of radioactive waste

  • Treatment facility by precipitation of liquid radioactive waste contaminated with natural Uranium generated from CANDU fuel fabrication (FCN Pitesti);
  • Incineration facility of solid waste contaminated with natural Uranium;
  • Treatment facility by evaporation of low level liquid waste;
  • Facility for cementation of solid radioactive waste and of radioactive concentrate resulted by evaporation ;
  • Treatment-conditioning plant of organic liquid waste contaminated with tritium;
  • Conditioning facility for bituminization of spent ion resins from the TRIGA reactor and other nuclear facilities;
  • Small scale mobile facility for the decontamination of small quantities of aqueous liquid waste.

 

Experimental Facilities

Pilot installation for treatment by reverse osmosis of liquid radioactive

  • Pilot installation for treatment by reverse osmosis of liquid radioactive waste;
  • High frequency induction melting facility for testing glass embedding of different types of radioactive waste;
  • Sepa CF Membrane Element Cell for liquid aqueous waste purification, a lab scale cross flow filtration unit designed to simulate the flow dynamics of larger, commercially available membrane elements such as industrial spiral wound membrane elements.

Laboratory equipment

  • System for total combustion of radioactive waste samples contaminated with 14C and 3H, 307 PERKINELMER Model;
  • Microwave digestion system, SpeedWave4;
  • Multichannel gamma spectometer chain with hiperpur Ge detector and AntiCompton system;
  • Liquid scintillation analyzer, TriCarb 3110 TR;
  • Emission spectrometer with inductively coupled plasma, iCAP 6500;
  • X-ray fluorescence spectrometer, X (EDXRF), ARL QuantX;
  • Fluorimeter for uranium content determination, Fluorat – 02 - 2M;
  • Spectrophotometer UV-VIS;
  • Total Organic Carbon Analyzer, StarTOC;
  • Differential thermal analyser (DTA-TG), DTG-60/60H;
  • Experimental set-up for quatification of total nitrogen content in different solid and liquid waste by Kjeldahl method;
  • Fractional sample collector and lab-scale columns for studying the contaminant transport through different geologic formations;
  • Experimental set-up for determination of inorganic and organic C-14 content from different radioactive waste matrices.

ICP-OES to determine the elemental composition

Total Organic Carbon Analyzer

Liquid scintillation analyzer to determine the β emitters



Last modified: 20-02-2019.


SCIENTIFIC MEETINGS

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