Abstract
This paper deals with the source terms due to the escape of activated corrosion products from a first wall or shielding blanket primary cooling loop of the international thermonuclear experimental reactor (ITER) machine following a loss of coolant accident (LOCA). The assessment is based on the European multi-code methodological approach set up to estimate the environmental releases of the activated corrosion/erosion products involved in accident scenarios of a fusion machine. The radioactive inventories (RIs) associated with the activation products have been estimated via the anita inventory code, using updated cross-section and decay data libraries based on EAF-3 activation data. The process source terms (PSTs) relevant to the LOCAs are estimated by considering mechanisms leading to RI mobilization (e.g. corrosion/erosion). The impact of the main operating parameters of the primary cooling loops is assessed. The FUMO codes have been used to estimate the thermal hydraulic conditions inside the containment. The PST transport and deposition in the containment are evaluated by the naua code in order to assess the released fraction from the last containment (reactor building).
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