INTERGRANULAR FILMS AND PORE SURFACES IN SYNROC C - STRUCTURE, COMPOSITION, AND DISSOLUTION CHARACTERISTICS

被引:23
作者
COOPER, JA [1 ]
COUSENS, DR [1 ]
HANNA, JA [1 ]
LEWIS, RA [1 ]
MYHRA, S [1 ]
SEGALL, RL [1 ]
SMART, RSC [1 ]
TURNER, PS [1 ]
WHITE, TJ [1 ]
机构
[1] GRIFFITH UNIV,SCH SCI,NATHAN,QLD 4111,AUSTRALIA
关键词
RADIOACTIVE MATERIALS - Storage;
D O I
10.1111/j.1151-2916.1986.tb04745.x
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
SYNROC C is a titanate ceramic being developed as an alternative to borosilicate glasses, for the disposal of high-level radioactive waste (HLW) produced by the reprocessing of spent commercial reactor fuel. The current paper is an appraisal of the contribution that waste elements, which have undergone segregation into intergranular films and pores, make toward the overall dissolution rate of HLW species from synroc.
引用
收藏
页码:347 / 352
页数:6
相关论文
共 27 条
[1]   STRUCTURE OF HIGH-ANGLE GRAIN-BOUNDARIES IN METALS AND CERAMIC OXIDES [J].
BALLUFFI, RW ;
BRISTOWE, PD ;
SUN, CP .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1981, 64 (01) :23-34
[2]   CERAMIC MATERIALS FOR THE IMMOBILIZATION OF NUCLEAR WASTE [J].
CLARKE, DR .
ANNUAL REVIEW OF MATERIALS SCIENCE, 1983, 13 :191-218
[3]   DETECTION OF THIN INTERGRANULAR FILMS BY ELECTRON-MICROSCOPY [J].
CLARKE, DR .
ULTRAMICROSCOPY, 1979, 4 (01) :33-44
[5]   APPLICATION OF ELECTRON-MICROSCOPY TO THE PROCESSING OF CERAMIC MATERIALS [J].
CLARKE, DR .
ULTRAMICROSCOPY, 1982, 8 (1-2) :95-107
[6]   CONTINUOUS-FLOW LEACHING STUDIES OF CRUSHED AND CORED SYNROC [J].
COLES, DG ;
BAZAN, F .
NUCLEAR TECHNOLOGY, 1982, 56 (02) :226-237
[7]   MICROSTRUCTURAL CHARACTERIZATION OF SYNROC-C AND SYNROC-E BY ELECTRON-MICROSCOPY [J].
COOPER, JA ;
COUSENS, DR ;
LEWIS, RA ;
MYHRA, S ;
SEGALL, RL ;
SMART, RS ;
TURNER, PS ;
WHITE, TJ .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1985, 68 (02) :64-70
[8]  
KESSON SE, 1984, SCI BASIS NUCL WASTE, V7, P507
[9]   HIGH-ALUMINA TAILORED NUCLEAR WASTE CERAMICS [J].
MORGAN, PED ;
CLARKE, DR ;
JANTZEN, CM ;
HARKER, AB .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1981, 64 (05) :249-258
[10]  
Oversby V.M., 1982, RADIOACT WASTE MANAG, V2, P223