ICN - Pitesti


Main research areas:

  • Development of the databank comprising the exploitation events of the  NPP equipped with CANDU 600 reactor;
  • Defining and modeling the degradation mechanism of important/critical components and developing methods of diagnosis;
  • Development of lifetime assessment methodologies of NPP components;
  • Assessment of the components aging effects on nuclear safety at a CANDU 600 type NPP;
  • Development of environment qualification technologies of materials and equipment for the NPP;
  • Development of components rehabilitation technologies, systems and structures affected by aging;
  • Prolonging the nuclear power plant durability over the designed lifetime period by using performing concrete and the analysis of the effects of the structures aging;
  • Development of a databank comprising the degradation mechanisms of components, systems and structures CANDU 6 NPP due to aging;
  • Development of surveillance and monitoring innovative techniques of the NPP components and systems;
  • Aging management of electric cables;
  • Magneto hydrodynamics cooled fast reactor lead (LFR).

Main research results:

  • Studies related to the behavior of the spacer bracket spacer simulator in the geometry similar to the central intermediary elastic coupling of a fuel channel assembly reproduced in laboratory conditions;
  • Local fingerprinting device of the inside surface of the generator tube in the chuck / plate rolled in tubular plate (experimental and testing model);
  • Trials for forming the ice plug in the Dn 200 mm pipe;
  • Trials on the assembly of recovery devices of the aged thermal insulation in the SLCD coil assemblies;
  • Analysis of the aging behavior of the splash collector of the 3332-TK1/TK2 monitoring the reduction of the thermo-mechanic stress generated by the water injection.
  • Inspection, monitoring and assessment of the aging of the electrical wiring;`
  • Aging management of electric cables ;
  • Maintenance of the MDI databank (Degradation Mechanisms through Aging);
  • Estimation of the impact of the air heating from C/R at the higher rates by increasing the thermal insulation thickness with ½"up to 1" at the Pressurizer, Heater and Degasser/Condenser;
  • Development of the identification method through the analysis of the noises of the absolute pressure transducers of the frequencies of the vibrations induced through the flow of a liquid through the pipe.

Contact: IDT I Tiberiu GYONGYOSI; e-mail: tiberiu.gyongyosi@nuclear.ro

Last modified: 06-02-2014.


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