核电厂放射性可燃废物等离子体玻璃固化配方初步研究

辐射防护 ›› 2015, Vol. 35 ›› Issue (5): 262-266.

核电厂放射性可燃废物等离子体玻璃固化配方初步研究

陈明周, 白冰, 刘夏杰, 吕永红, 黄文有

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

收稿日期:2015-01-21 出版日期:2015-09-20 发布日期:2024-10-22
作者简介:陈明周(1978—),男, 2002年毕业于广州大学物理与电子工程学院物理教育专业,2010年7月毕业于中国科学院等离子体物理研究所等离子体物理专业,获博士学位,高级工程师。E-mail: chenmingzhou@cgnpc.com.cn

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

Chen Mingzhou, Bai Bing, Liu Xiajie, Lv Yonghong, Huang Wenyou

China General Nuclear Power Corporation, China Nuclear Power Technology Research Institute, Guangdong Shenzhen 518124

Received:2015-01-21 Online:2015-09-20 Published:2024-10-22

摘要/Abstract

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、SiO₂、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。

关键词: 核电厂, 可燃废物, 玻璃固化, 等离子体

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

中图分类号:

TL941+.113

陈明周, 白冰, 刘夏杰, 吕永红, 黄文有. 核电厂放射性可燃废物等离子体玻璃固化配方初步研究[J]. 辐射防护, 2015, 35(5): 262-266.

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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