This paper summarizes the work done to update the PACTOLE code, developed for Pressurized Water Reactors (PWRs) to predict the level of activated corrosion products in their cooling loops. The aim is to use it in safety analysis 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' experimental 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 collective dose to the staff in the supporting activities for the Non-Site Specific Safety Report n.2 (NSSR-2).
|Pages (from-to)||733 - 737|
|Number of pages||5|
|Issue number||3 pt 2|
|Publication status||Published - Nov 1998|
All Science Journal Classification (ASJC) codes
Di Pace, L., Tarabelli, D., & You, D. (1998). Development of the PACTITER code and its application to the assessment of the ITER divertor cooling loop corrosion products. Fusion Technology, 34(3 pt 2), 733 - 737.