核电厂放射性可燃废物等离子体玻璃固化配方初步研究  

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

作　　者：陈明周[1] 白冰[1] 刘夏杰[1] 吕永红[1] 黄文有[1] 

机构地区：[1]中国广核集团中科华核电技术研究院有限公司,广东深圳518124

出　　处：《辐射防护》2015年第5期262-266,273,共6页Radiation Protection

摘　　要：为了获得放射性可燃废物等离子体玻璃固化的配方,选取核电厂现场的棉制品、吸水纸、塑料、橡胶和环氧树脂为对象,采用高温熔融对其焚烧灰进行玻璃固化。结果表明,当灰分、Si O2、B2O3、Na2O的质量比为0.4∶0.4∶0.1∶0.1时,得到玻璃固化体的密度为2.5 g/cm3,抗压强度为90 MPa,Sr、Cs、Co等示踪元素归一化浸出率均小于0.535 g·m-2·d-1,可用于50 kg/h规模的等离子体熔融系统实验研究。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,Si O2,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 /cm3 of density,90 MPa of compress strength and less than 0. 535 g·m- 2·d- 1of 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.

关 键 词：核电厂 可燃废物 玻璃固化 等离子体 

分 类 号：TL941[核科学技术—辐射防护及环境保护]