The cross connection between passive systems described in Sections 2 and 3 and phenomena identified in Section 4.1 can be derived from Table 2, namely considering the first and the last column. This is consistent with the second bullet under the heading of the present section as elements of aims of Section 4.

In addition, an effort has been made to homogenize the nomenclature adopted by different designers: having defined the type of passive safety system (for core decay heat removal and for containment cooling and pressure suppression) and the related (key) phenomena, in column 3 of Table 2. The passive safety systems are listed and named according to the nomenclature provided by the designers (Annexes I to XX).

In the column 2 of Table 2 the passive safety systems are foreseen in ‘various advanced water cooled nuclear power plants’ (part I of annexes of the present document, i. e. Annexes I to XIII) are distinguished from ‘integral reactor systems’ (part II of annexes of the present document, i. e. Annexes XIV to XX).

As in the case of the previous table, the content of Table 2 is self-standing and directly understandable including the supporting description provided in Sections 2 and 3 and in Annexes I to XX (as already mentioned). The following additional items should be noted:

• An attempt has been made to list in the column 2 all passive systems installed in the reactors described in Annexes I to XX. However, the current stage of the design and the different level of detail in the descriptions prevent the possibility of an imperfection-free list. This is particularly true in relation to the accumultors (first row in the table).

• The variety of definitions adopted by designers for passive systems is wider than what is considered here.