TESTING OF LITHIUM TITANATE AS AN ALTERNATE BLANKET MATERIAL

被引:88
作者
MILLER, JM
HAMILTON, HB
SULLIVAN, JD
机构
关键词
D O I
10.1016/0022-3115(94)90961-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Lithium titanate (Li2TiO3) has been investigated as an alternate ceramic blanket material to Li2ZrO3. Relatively high density 1.2 mm spheres have been produced using an extrusion/tumbling method. High-strength spheres were obtained as determined by testing following thermal cycling. Tritium release was investigated in post-irradiation anneals. The effects of heating rate, sweep-gas composition and material characteristics were investigated. The results indicate good tritium release characteristics for this material, similar to Li2ZrO3.
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页码:877 / 880
页数:4
相关论文
共 10 条
[1]   MODELING, ANALYSIS AND EXPERIMENTS FOR FUSION NUCLEAR TECHNOLOGY [J].
ABDOU, MA ;
HADID, AH ;
RAFFRAY, AR ;
TILLACK, MS ;
IIZUKA, T ;
GIERSZEWSKI, PJ ;
PUIGH, RJ ;
SZE, DK ;
PICOLOGLOU, B .
FUSION ENGINEERING AND DESIGN, 1988, 6 (01) :3-64
[2]  
BOTTER F, 1992, 1LTH P S FUS TECHN, P924
[3]  
FINN PA, 1981, 9TH P S ENG PROBL FU, V2, P1200
[4]  
KOPASZ JP, 1994, J NUCL MATER, P212
[5]  
Miller J.M., 1991, FUSION TECHNOL, V19, P996, DOI [10.13182/FST91-A29472, DOI 10.13182/FST91-A29472]
[6]   POSTIRRADIATION TRITIUM RECOVERY FROM LITHIUM CERAMIC BREEDER MATERIALS [J].
MILLER, JM ;
BOKWA, SR ;
VERRALL, RA .
JOURNAL OF NUCLEAR MATERIALS, 1986, 141 :294-299
[7]  
MILLER JM, 1994, J NUCL MATER, P212
[8]  
SLAGLE OD, 1993, 1MTH P S FUS TECHN, P1499
[9]   CANADIAN CERAMIC BREEDER SPHERE-PAC TECHNOLOGY - CAPABILITY AND RECENT RESULTS [J].
SULLIVAN, JD ;
BRAYMAN, CL ;
VERRALL, RA ;
MILLER, JM ;
GIERSZEWSKI, PJ ;
LONDRY, F ;
SLAVIN, A .
FUSION ENGINEERING AND DESIGN, 1991, 17 :79-85
[10]  
VERRALL RA, 1993, P INT WORKSHOP CERAM, P225