Four production methods of 177Lu, e.g. from natural and enriched Lu and from natural and enriched Yb were considered and experimentally evaluated. The samples of all 4 materials were irradiated in a nuclear reactor, the activity of 177Lu measured and compared with a computed one. In the case of 177Lu produced from enriched Lu target the amount of activity obtained is 40 to 70% higher than calculated. The results achieved will be applied for the optimization of 177Lu production for medical applications.