The Joint European Torus (JET) is operated with the ITER-Like Wall (JET-ILW): beryllium in the main chamber and tungsten in the divertor in order to replicate materials for ITER. It was present systematic and quantitative study of tritium retention in dust and divertor tiles of ILW by means of tritium imaging plate technique to assess tritium level in individual particles and, by a full combustion method to determine the total tritium amount in the tiles and dust. Using these two different techniques, it was found that the poloidal distributions of the surface and bulk trapped tritium are quite different. The total tritium activities show significant differences between the JET operation with ILW and the earlier operation with the carbon wall (JET-C) indicating that tritium retention is significantly decreased in the operation with ILW. The approximate amount of tritium in the dust and tiles was also measured.