Trilaurylamine nitrate diluted in dodecane is considered as an extracting agent for plutonium. The use of this solvent is proposed for a tail-end plutonium recovery from irradiated uranium solutions which have already been purified by one or more TBP cycles. Mention is made of general properties of the solvent. The study of the stripping of plutonium is emphasized. The first choice stripping solution is a mixture of sulfuric and nitric acid which gives a final concentrated and purified Pu4+ solution. Some alternative purification flowsheets are given. They show that a decontamination factor of 104 can be attained for Zr-Nb and uranium. Kinetics of the extraction and radiolytic degradation of the solvent are briefly discussed.