二酸化ウラン分散-黒鉛系燃料の再処理, (III)

塩化物揮発法

抄録

The chloride-volatility process was applied to the processing of irradiated UO₂-graphite fuel elements, in which most of fission products were introduced into the graphite matrix by fission recoil.
In proper conditions, 99% of UO₂ in the sample was chlorinated with CCl₄ vapor. However, the major objective in the present study was to investigate the behavior of the fission products during the chlorination. It was elucidated that besides the postirradiation heating itself the existence of the chlorinating agent was additionally effective in the migration of fission products in the graphite matrix.
The possibility of low temperature chlorination with chlorine gas was also studied.