• "Best-estimate" analyses of the damage to the nuclear fuel cladding and evaluation of the fission product release to the coolant;
  • 3D FEM modeling of fuel rods, respectively fuel assemblies;
  • Involvement in international programs organized by ECand OECD / NEA in the field of experimental research on fuel behavior in operational or DBA conditions.

 


Keeping your site working well

This website uses cookies to provide social media functions and analyse the visit rate. By clicking on the "Enable all cookies" button, you agree to storage and use of cookies. Detailed information about cookies see here.