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首页> 外文期刊>Radiochimica Acta: International Journal for Chemical Aspects of Nuclear Science and Technology >The isolation of Mo-99 from fission material for use in the Mo-99/Tc-99m generator for medical use
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The isolation of Mo-99 from fission material for use in the Mo-99/Tc-99m generator for medical use

机译:Mo-99与裂变材料的隔离,用于医疗用Mo-99 / Tc-99m发生器

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摘要

Molybdenum-99 is an important radionuclide which is used in nuclear medicine and a new method is presented for the isolation and purification of Mo-99 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 ill 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, Mo-99, I-131 and the radionuclides of alkali-soluble elements ill the sodium hydroxide solution were separated from the uranium and radionuclides of the alkali ne-insoluble elements by filtration. The radionuclides of molybdenum and iodine were separated by anion exchange chromatography, ill alkaline medium, front the bulk aluminium and radionuclides of other elements, such as barium, strontium and tellurium. Mo-99 was selectively eluted with a slightly alkaline lithium sulphate solution, leaving the iodine radionuclides on the resin. The Mo-99 eluant was acidified with oxalic acid and nitric acid and Mo-99 separated from the remaining aluminium and other radionuclides by anion exchange chromatography, in acid medium. After elution of Mo-99, again with a slightly alkaline lithium sulphate solution, the eluant was acidified with nitric acid, Mo-99 concentrated on a chelating resin column and finally eluted with ammonia and evaporated to obtain (MoO3)-Mo-99 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.
机译:钼99是一种重要的放射性核素,用于核医学,提出了一种新的从裂变材料中分离纯化钼99的方法。开发该方法是为了适合南非核能公司(NECSA)的需要,并且还因为大多数其他方法已获得专利,因此不能在NECSA中使用。一种铀-铝合金,包铝。用作目标,并且该目标在核反应堆中辐照了几天。冷却后。为了使短寿命的放射性核素衰变,将目标物质溶解在氢氧化钠溶液中。放射性k气和氙气收集在活性炭上并储存,直到两种气体都腐烂为止。通过过滤将铝,Mo-99,I-131和氢氧化钠溶液中的碱溶性元素的放射性核素与碱ne不溶性元素的铀和放射性核素分离。钼和碘的放射性核素通过阴离子交换色谱法,在弱碱性介质中,大量的铝和其他元素(如钡,锶和碲)的放射性核素分离。用微碱性的硫酸锂溶液选择性洗脱Mo-99,使碘放射性核素留在树脂上。将Mo-99洗脱液用草酸和硝酸酸化,然后在酸性介质中通过阴离子交换色谱将Mo-99与其余的铝和其他放射性核素分离。 Mo-99洗脱后,再次用弱碱性硫酸锂溶液洗脱,洗脱液用硝酸酸化,Mo-99在螯合树脂柱上浓缩,最后用氨水洗脱并蒸发,得到(MoO3)-Mo-99然后将其溶于稀氢氧化钠溶液中。最终产物的纯度在英国和欧洲药典的规定之内,并且不需要进一步的纯化步骤,例如升华。

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