Development of the PACTITER code and its application to the assessment of the ITER divertor cooling loop corrosion products

This paper summarizes the work done to update the PACTOLE code, developed f or Pressurized Water Reactors (PWRs) to predict the level of activated corr osion products in their cooling loops. The aim is to use it in safety analy sis for the International Thermonuclear Experimental Reactor (ITER) project . In particular the adaptation has focused on the implementation of copper as a new element in the code by using the findings obtained from "ad hoc" exp erimental tests. The updated release of the code, named PACTITER, has been extensively used to predict in particular the source term inventory of the ITER divertor primary heat transfer system (PHTS) and the related collectiv e dose to the staff in the supporting activities for the Non-Site Specific Safety Report n.2 (NSSR-2).