الفهرس 
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Abstract
99Mo decays to the daughter 99mTc which is frequently used in nuclear medicine. Alumina columns loaded with 99Mo are still the generators most commonly used to elute 99111Tc with
0.9% saline solution. The need for high activity 99:nTc generators and the limited capacity of alumina for molybdate ions made 235U fission reaction the best source to provide high specific activity 99Mo.
235U fission reactions results in the production of more
than 35 elements with approximately 200 no carrier added radionuclides including 99Mo with 6.25% fission yield. chromatographic column techniques are generally preferred for the separation of fission-99Mo than solvent extraction and precipitations. In this respect, 99Mo was separated from different fission solutions by incorporation into 12-molybdocerate (IV) matrix packed in the form of a chromatographic column . The obtained 99Mo matrices are seriously contaminated with the radionuclides of 131 1321, 132Te, 95Zr, 95Nb, 103Ru,.... etc. Therefore, additional purifications of 99Mo are needed using different washing solutions.
The sorption I desorption behaviour of some relevant fission products on 12-molybdocerate was investigated by static and dynamic methods to determine the proper washing solutions to get rid of the interfering radionuclides with 99Mo .
The process of production of fission 99Mo includes the following main steps; the uranyl nitrate target irradiation, dissolution, control of the chemical composition of the solute, chromatographic processing using 12-molybdocerate column matrix and finally decontamination of the bed matrix from the