[en] The metabolic behaviour of inhaled uranium is studied. Using a particular analytical method applied to the models and dose assessment methods recommended by ICRP, the organ committed equivalent dose and effective equivalent dose are calculated. The exact ALI and DAC are derived from there. In the paper, the influence that various parameters have on those results are considered for the specific case of a particular nuclear element fabrication factory. Different AMAD and solubility type of inhaled material are specially analyzed. The results show the paramount importance of some of these parameters on the secondary and derived dose limits. Relationships between the real intake, as a fraction of ALI, and the lung retention or urine excretion are shown for different cases and intake forms hypothesis. Minimum detectable intakes with the available experimental techniques are then established. The results shown in the papel are a useful tool to help on the decision on the type and frequency of the individual monitoring techniques to be established in different circumstances. (Author)