文章信息/Info

Title:

International Research Progress on Nuclear Waste Vitrification: A Review

作者:

徐凱

韓國浦項工科大學 先進核能中心 材料科學與工程學院

Author(s):

XU Kai

Division of Advanced Nuclear Engineering, Department of Materials Science and Engineering, Pohang University of Science and Technology-POSTECH

關鍵詞:

放射性廢物; 玻璃固化; 硼硅酸鹽玻璃; 固化體

DOI:

10.7502/j.issn.1674-3962.2016.07.01

文獻標志碼:

A

摘要:

玻璃體對不同元素有著廣泛的包容性、且具有良好的耐久性，另外，玻璃生產工藝簡單，易于遙控操作，因而，玻璃固化技術是目前國際上唯一工業應用且發展最成熟的高放廢液處理技術。本文從材料學的角度，介紹了玻璃固化核廢料的機理及設計核廢料玻璃固化體的基本原則，綜述了玻璃固化體近年的國際研究進展。重點研究方向包括：(1)以提高核廢料負載量為目標，研究玻璃體對核廢料的承載能力；(2)最大化核廢料玻璃產率，研究玻璃爐料熔融物理化學反應；(3)確保核廢料玻璃長期貯存的安全，研究玻璃腐蝕機理，建立長期腐蝕行為模型，提供玻璃固化體安全評價方法。最后，對核廢料玻璃固化體今后的研究發展方向做了展望。

Abstract:

Vitrification is the well-developed and the only kind of technology to industrially immobilize the nuclear wastes originating from civil and military spent fuel reprocessing, because the glass waste form enables to incorporate a very large range of elements, has the good long-term durability to resist the chemical corrosion, and could be produced with the relative simple processes under the remote control. In the view point of materials science and technology, this paper introduced the glass immobilization mechanism and principles to design glass waste form, and then reviewed the recent international research progress on glass waste form. The main efforts includes (i) ability to accommodate the waste to improve the waste loading, (ii) melter feed reactions to maximize the rate of melting, and (iii) the corrosion mechanism and the long-term behavior to ensure the safe disposal. Finally, future trends and options in waste vitrification were prospected.