发明名称 Treating nuclear fuel comprising nuclear fissionable material, silicon carbon and optionally carbon, comprises contacting the fuel with mixture of chlorine and oxygen to eliminate the silicon carbon and the carbon present in the fuel
摘要 #CMT# #/CMT# Treating a nuclear fuel comprising a nuclear fissionable material, silicon carbon and optionally carbon, comprises: contacting the fuel with a mixture of chlorine and oxygen at a temperature strictly less than 950[deg] C, preferably 400-900[deg] C, to eliminate the silicon carbon and the carbon if it is present in the fuel. #CMT#USE : #/CMT# The process is useful for the treatment of nuclear fuel. #CMT#ADVANTAGE : #/CMT# The process can reprocess the fuels. The process is effective, clean, cost effective and very quick process. #CMT#INORGANIC CHEMISTRY : #/CMT# Preferred Process: The process comprises eliminating the silicon and carbon to generating a gas emission, determining the chemical composition of the emission and modifying the composition of the mixture of chlorine and oxygen according to the determination. Preferred Components: The mixture of chlorine and oxygen comprises 1-30% of oxygen and 70-99% of chlorine. The quantity of silicon carbon is to be eliminated varying during treatment, and the mixture of chlorine and oxygen is modified to follow the variation. The fuel comprises silicon carbon and carbon in which at a moment (M) of the treatment comprising (a) eliminating more silicon carbon than carbon or (b) eliminating more carbon than silicon carbon and in which at the moment the mixture of chlorine and oxygen is modified to produce more chlorine than oxygen in step (a) or more oxygen than chlorine in the step (b). The nuclear fuel is tri-structural-isotropic (TRISO) or bi-structural isotropic (BISO), preferably TRISO particles or BISO comprising silicon carbon and carbon. The particles comprise a core of fissionable material and a sheath comprising an alternance of carbon layers and silicon carbon, where the treatment is a desheathing of particles. The fissionable material is actinide oxides, actinide oxides, actinide carbides and actinide oxycarbides. The nuclear fuel is a fuel with heterogeneous silicon carbon, where the treatment being a treatment for matrix elimination.
申请公布号 FR2907588(A1) 申请公布日期 2008.04.25
申请号 FR20060054464 申请日期 2006.10.24
申请人 COMMISSARIAT A L'ENERGIE ATOMIQUE ETABLISSEMENT PUBLIC A CARACTERE INDUSTRIEL ET COMMERCIAL 发明人 BOURG STEPHANE;PERON FREDERIC
分类号 G21C19/38 主分类号 G21C19/38
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