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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