Chapter 17 – Immobilisation of Radioactive Wastes in Glass

摘要: Publisher Summary This chapter on the whole gives an excellent account of vitrification process used for immobilization radioactive wastes. Vitrification involves melting waste materials with glass-forming additives so that final vitreous product incorporates contaminants in its macro- and micro-structure. Hazardous constituents are immobilized either by direct incorporation into glass structure or encapsulation. Encapsulation is usually carried out dispersion insoluble compounds melt form produced a composite material (GCM) not homogeneous glass. The reliability radionuclide characterized rate at which radionuclides can be released from during long-term storage. highest degree volume reduction safety achieved through although this most complex expensive method requiring relatively high initial capital investment. Furthermore, turns to discussion types their properties. Two main have been accepted nuclear immobilization–—borosilicates phosphates. exact compositions glasses tailored preparation melting, avoidance phase separation uncontrolled crystallization, acceptable leaching resistance. selection borosilicates based flexibility borosilicate regards loading ability incorporate many different kinds elements, coupled good ability, chemical durability, mechanical integrity, excellent thermal radiation stability. Molten phosphate highly corrosive refractory linings, behavior has limited application. Novel Fe–Pb–phosphate particularly attractive due accommodate enhanced amounts oxides durability.