A two-step chromatographic technique was elaborated to isolate144Ce,144Pr from a solution of uranium fission products in 6M HNO3. The oxidation to Ce(III) by bromate and selective adsorption of144Ce(IV) on anion exchange column were used to concentrate and purify144Ce. Some impurities of uranium,95Zr,95Nb,106Ru remain in144Ce solution after the first step of its isolation. The final purification is achieved by passing the 6M HNO3 solution of144Ce(IV) through the HDEHP-coated teflon column. The decontamination factors of144Ce from main fission products are given. 7.2 mCi of (144Ce+144Pr) are recovered from each gram of irradiated uranium trioxide with the yield greater than 99%. An improvement of known generator was carried out to elute a purer144Pr from maternal144Ce(IV) adsorbed on the anion exchange column.