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The Fuel Cycle of the Fission Molybdenum Production

 

作者: G. Bernhard,   W. Boessert,   T. Grahnert,   O. Hladik,   R. Krompass,  

 

期刊: Isotopenpraxis Isotopes in Environmental and Health Studies  (Taylor Available online 1990)
卷期: Volume 26, issue 3  

页码: 93-97

 

ISSN:0021-1915

 

年代: 1990

 

DOI:10.1080/10256019008624240

 

出版商: Taylor & Francis Group

 

关键词: enriched uranium;fabrication;fission products;fuel cycle molybdenum 99;nuclear facilities;reprocessing;spent fuel elements

 

数据来源: Taylor

 

摘要:

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+xdispersion, and fabrication of the new target elements. The content of nuclear material is regularly being examined by the proliferation agreement.

 

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