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Dujardin, T.; Lonchampt, G.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction du Cycle du Combustible1990
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Direction du Cycle du Combustible1990
AbstractAbstract
[en] The french Chemex process for uranium enrichment is found upon chemical exchange between valences 3 and 4 of uranium and operated with countercurrent liquid-liquid extraction with double reflux. The main problems encountered in developing this process were to achieve electrochemical reduction on mercury cathode, master phases stability and increase performances of pulsed columns with perforated plates. The main results obtained are: - a volumic efficiency over 300 SWU/yr.m3 in the isotopic cascade - an energy consumption of 375 KWh-el/SWU with 40% in low grade thermal form. A 500 000 SWU/year plant design, dedicated to reprocessed uranium, is presented, leading to a SWU cost of 900 FF/SWU. A ten times larger plant, (5 MSWU/yr), for natural uranium, give a production cost of 650 FF/SWU
Primary Subject
Source
1990; 30 p; International Symposium on Isotope Separation and Chemical Exchange Uranium Enrichment; Tokyo (Japan); 28 Oct - 1 Nov 1990
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, CHEMICAL REACTIONS, DIAGRAMS, EQUIPMENT, EVEN-ODD NUCLEI, EXTRACTION APPARATUSES, HEAVY NUCLEI, INFORMATION, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MINUTES LIVING RADIOISOTOPES, NUCLEI, RADIOISOTOPES, SEPARATION EQUIPMENT, SEPARATION PROCESSES, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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