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In consideration of economy and safeguard regulations the nuclear fuel has to be recycled. It was therefore nessesary to develop a technological procedure which permits the recovery of uranium from the waste solution arising from fission molybdenum production. The so-called AMOR-facility includes three main parts: 1. The dissolution of an irradiated fuel element of a research reactor, the separation of fission molybdenum and a long-lime storage of this fuel element solution. 2. The recovery of uranium from solution by an extraction-reextraction process with tri-n-butylphosphate. 3. Producing the AI/UO2+x dispersion, and fabrication of the new target elements. The content of nuclear material is regularly being examined by the proliferation agreement.

In the Central Institute of Nuclear Research Rossendorf (CINR) a special solvent extraction procedure has been developed for recovery of residual uranium from waste solutions of fission molybdenium-99 production. After an inactive test period the corresponding facility was put into operation in September 1985. Obtained operating results, as well as experience gained up to now will be introduced and discussed in this report. Emphasis will be concentrated on: - Process technology - Fission material-fission product-decontamination - Operating reliability - Nuclear material throughput