Development of the PACTITER code and its application to safety analyses of ITER Primary Cooling Water System

L. Di Pace, F. Dacquait, P. Schindler, V. Blet, F. Nguyen, Y. Philibert, B. Larat

Research output: Contribution to journalArticle

14 Citations (Scopus)


The PACTITER code derives from the PACTOLE code, developed by the CEA for predicting activated corrosion products (ACPs) in PWR primary circuits. The operating conditions, material compositions and water chemistry of the various Primary Heat Transfer Systems (PHTS) of the International Thermonuclear Experimental Reactor (ITER) made mandatory the adaptation of the PACTOLE code. PACTITER was developed on the basis of dedicated experiments, namely devoted to determine copper solubility and stainless steel release in the ITER primary cooling systems conditions, which are rather different from those in PWR (i.e. water chemistry and temperatures). The PACTITER code has been extensively used in support of the ITER Generic Site Safety Report (GSSR) in the field of accident analysis and worker collective dose assessment. © 2006 Elsevier B.V. All rights reserved.
Original languageEnglish
Pages (from-to)237 - 247
Number of pages11
JournalFusion Engineering and Design
Issue number3
Publication statusPublished - Apr 2007
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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