Abstract
TN International and International Nuclear Services started commonly in early 2000s the Fuel Integrity Project (FIP) to develop a methodology to assess the response of fresh and used light water reactor (LWR) fuel assemblies (F/A) during 9 m regulatory drops. The analysis of experimental knowledge acquired from fresh F/A behaviour during drop tests and various mechanical tests on fresh and used fuel rod (F/R) samples has led to the elaboration of FIP methodology, allowing the assessment of F/A damage during lateral and axial accident drops of a packaging. In particular, the developed pessimistic mechanical evaluations based on comparison with results of reference bending tests permit to assess, using elastic beam formulas, F/R rupture risks in intergrid bending or Euler buckling configurations. These simple, but interesting, static mechanical approaches can be used for several possible loadings and boundary conditions. They take into account the following: the F/R maximum possible deflection in cask lodge...
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