[en] The main purpose of the development of the advanced nuclear fuel cycle is to reduce the environment risk by the minor actinides, such as Np, Am and Cm. The level of the minor actinides must be held down as low as possible by means of burning and annihilating in the fast reactor and so on. A, fuel irradiation test for MOX fuel containing 1% Am is being performed experimentally in the fast test reactor JOYO of JNC. Moreover, irradiation tests of MOX fuels containing up to 5% Am (Am-MOX fuels) are planned in JNC. Therefore, raw material for these fuels was prepared. Am-241 is generated from a disintegration of Pu-241 and gradually accumulated in MOX fuel. Am-241 was extracted from MOX scraps by a PUREX method and a TRUEX method using CMPO/TBP/n-dodecane solvent. The raw material of Am-MOX fuels was prepared from about 12 g of collected Am by the TRUEX method and equal quantities of Pu and U. It was confirmed that the extraction behavior of Am by a calculation code for the TRUEX method agreed with the experimental data in extraction area. (authors)