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

L. Di Pace (1) , F. Dacquait (2) , P. Schindler (2) , V. Blet (2) , F. Nguyen (2) , Y. Philibert (2) , B. Larat (2)

1 Associazione EURATOM-ENEA
2 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

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. This new code, called PACTITER, has then been developed on the basis of dedicated experiments, and particularly, in order to determine the stainless steel release, which depends on the thermal-hydraulic conditions (fluid temperature and Reynolds number). The PACTITER code has been used in support of the ITER Generic Site Safety Report (GSSR) in the field of accident analysis and worker collective dose assessment.

Mots clés: safety analysis; ITER; PACTITER; ACPs; PACTOLE

Domaines: Physique Nucléaire Expérimentale [nucl-ex]; Physique Nucléaire Théorique [nucl-th]

L. Di Pace, F. Dacquait, P. Schindler, V. Blet, F. Nguyen, et al.. Development of the PACTITER code and its application to safety analyses of ITER Primary Cooling Water System. Fusion Engineering and Design, 2006, 82 (3), pp.237-247. ⟨10.1016/j.fusengdes.2006.11.002⟩. ⟨cea-02356047⟩