核电厂放射性可燃废物等离子体玻璃固化配方初步研究

Abstract

Abstract: To develop glass formulations for plasma vitrification of combustible low and intermediate level radioactive wastes form nuclear power plants, 5 kinds of simulated wastes were selected and then incinerated. The incineration ash was vitrified by high temperature melting. Analysis of the glasses discloses that when the mass ratio of incineration ash, SiO₂, B₂O₃ and Na₂O equals to 0.4∶0.4∶0.1∶0.1(4^#), the glassy waste form shows the best performance with 2.5 g/cm³of density, 90 MPa of compress strength and less than 0.535 g·m^-2·d^-1 of normalized elemental leaching rate for Cs, Sr Co, etc. It can be concluded that the 4^# formulation seems to be the most preferable one for vitrification tests on the 50 kg/h plasma system.

Key words: nuclear power plants, combustible wastes, vitrification, plasma

CLC Number:

TL941+.113

Chen Mingzhou, Bai Bing, Liu Xiajie, Lv Yonghong, Huang Wenyou. Development of glass formulation for plasma vitrification of combustible solid wastes from nuclear power plants[J].RADIATION PROTECTION, 2015, 35(5): 262-266.

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Development of glass formulation for plasma vitrification of combustible solid wastes from nuclear power plants

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