caa a22 4500 378907212 CHVBK 20180305123532.0 cr unu---uuuuu 161128e20040401xx s 000 0 eng 10.1524/ract.92.4.251.35589 doi (NATIONALLICENCE)gruyter-10.1524/ract.92.4.251.35589 The isolation of 99Mo from fission material for use in the 99Mo/99mTc generator for medical use [Elektronische Daten] [T.N. van der Walt, P. P. Coetzee] Molybdenum-99 is an important radionuclide which is used in nuclear medicine and a new method is presented for the isolation and purification of 99Mo from fission material. The method was developed to suit the needs of the Nuclear Energy Corporation of South Africa (NECSA) and also because most other methods had been patented and could therefore not be used at NECSA. A uranium-aluminium alloy, cladded in aluminium, served as a target and the target was irradiated in a nuclear reactor for several days. After a cooling period, in order to let the short-lived radionuclides decay, the target material was dissolved in a sodium hydroxide solution. The radioactive krypton and xenon gases were collected on activated carbon and stored until both gases had decayed. Aluminium, 99Mo, 131I and the radionuclides of alkali-soluble elements in the sodium hydroxide solution were separated from the uranium and radionuclides of the alkaline-insoluble elements by filtration. The radionuclides of molybdenum and iodine were separated by anion exchange chromatography, in alkaline medium, from the bulk aluminium and radionuclides of other elements, such as barium, strontium and tellurium. 99Mo was selectively eluted with a slightly alkaline lithium sulphate solution, leaving the iodine radionuclides on the resin. The 99Mo eluant was acidified with oxalic acid and nitric acid and 99Mo separated from the remaining aluminium and other radionuclides by anion exchange chromatography, in acid medium. After elution of 99Mo, again with a slightly alkaline lithium sulphate solution, the eluant was acidified with nitric acid, 99Mo concentrated on a chelating resin column and finally eluted with ammonia and evaporated to obtain 99MoO3 which was then dissolved in diluted sodium hydroxide solution. The purity of the final product was within the specifications of the British and European Pharmacopoiea and no further purification steps, such as sublimation, were required. © 2004 Oldenbourg Wissenschaftsverlag GmbH Laboratory techniques, experiments nationallicence Analytical chemistry nationallicence Inorganic chemistry nationallicence van der Walt T.N. aut Coetzee P. P. aut Radiochimica Acta/International journal for chemical aspects of nuclear science and technology Oldenbourg Wissenschaftsverlag GmbH 92/4-6/2004(2004-04-01), 251-257 0033-8230 92:4-6/2004<251 2004 92 ract https://doi.org/10.1524/ract.92.4.251.35589 text/html Onlinezugriff via DOI 1 research article jats NATIONALLICENCE 856 40 https://doi.org/10.1524/ract.92.4.251.35589 text/html Onlinezugriff via DOI NATIONALLICENCE 700 1- van der Walt T.N. aut NATIONALLICENCE 700 1- Coetzee P. P. aut NATIONALLICENCE 773 0- Radiochimica Acta/International journal for chemical aspects of nuclear science and technology Oldenbourg Wissenschaftsverlag GmbH 92/4-6/2004(2004-04-01), 251-257 0033-8230 92:4-6/2004<251 2004 92 ract CC0 http://creativecommons.org/publicdomain/zero/1.0 nationallicence BK010053 XK010053 XK010000 NATIONALLICENCE NATIONALLICENCE NL-gruyter