Method for coextracting uranium, plutonium and neptunium
Patent Information
- Authority / Receiving Office
- CN · China
- Current Assignee / Owner
- CHINA INSTITUTE OF ATOMIC ENERGY
- Publication Date
- 2012-11-14
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Abstract
Description
Technical field
[0001] The invention belongs to the technical field of nuclear fuel cycle, and specifically relates to a method for co-extraction of uranium, plutonium and neptunium. Background technique
[0002] 237 Np is a transuranium element, a fissile nuclear material, and one of the by-products of the reprocessing plant, with a half-life of 2.14×10 6 year. In a typical light water reactor spent fuel, each ton of spent fuel contains about 500-700 grams 237 Np; in fast reactor spent fuel, there are approximately 200 grams per ton of spent fuel 237 Np.
[0003] due to 237 Np is highly radioactive. In the nuclear fuel cycle, if it is used as nuclear waste for geological disposal after glass solidification, the disposal cost is high and it will have an incalculable impact on the ecological environment. And if it will be greater than 99% 237 Separating Np from spent fuel can greatly reduce the radioactive toxicity of nuclear waste and the cost of geological disposal. In addition,...