Mechanical properties of nuclear waste glasses

被引:28
作者
Connelly, A. J. [1 ]
Hand, R. J. [1 ]
Bingham, P. A. [1 ]
Hyatt, N. C. [1 ]
机构
[1] Univ Sheffield, Dept Mat Sci & Engn, Immobilisat Sci Lab, Sheffield S1 3JD, S Yorkshire, England
关键词
FRACTURE-TOUGHNESS TEST; INDENTATION FRACTURE; BOROSILICATE GLASS; IMMOBILIZATION; TEMPERATURE; EQUATIONS; BEHAVIOR; ENERGY;
D O I
10.1016/j.jnucmat.2010.11.034
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The mechanical properties of nuclear waste glasses are important as they will determine the degree of cracking that may occur either on cooling or following a handling accident. Recent interest in the vitrification of intermediate level radioactive waste (ILW) as well as high level radioactive waste (HLW) has led to the development of new waste glass compositions that have not previously been characterised. Therefore the mechanical properties, including Young's modulus, Poisson's ratio, hardness, indentation fracture toughness and brittleness of a series of glasses designed to safely incorporate wet ILW have been investigated. The results are presented and compared with the equivalent properties of an inactive simulant of the current UK HLW glass and other nuclear waste glasses from the literature. The higher density glasses tend to have slightly lower hardness and indentation fracture toughness values and slightly higher brittleness values, however, it is shown that the variations in mechanical properties between these different glasses are limited, are well within the range of published values for nuclear waste glasses, and that the surveyed data for all radioactive waste glasses fall within relatively narrow range. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:188 / 193
页数:6
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