Ceramics for fusion reactors: The role of the lithium orthosilicate as breeder

被引:17
作者
Carella, Elisabetta [1 ]
Hernandez, Teresa [1 ]
机构
[1] CIEMAT, Natl Lab Magnet Fus, Dept Mat, E-28040 Madrid, Spain
关键词
Lithium ceramics; Nuclear fusion; Blanket; Breeder; Ionic conductivity; Gamma irradiation; Electrochemical impedance spectroscopy (EIS); TRITIUM RELEASE; SILICATES; BLANKET; CONDUCTIVITY; IMPEDANCE; OXIDE; LI2O;
D O I
10.1016/j.physb.2012.07.013
中图分类号
O469 [凝聚态物理学];
学科分类号
070205 ;
摘要
Lithium-based oxide ceramics are studied as breeder blanket materials for the controlled thermonuclear reactors (CTR). Lithium orthosilicate (Li4SiO4) is one of the most promising candidates because of its lithium concentration (0.54 g/cm(3)), its high melting temperature (1523 K) and its excellent tritium release behavior. It is reported that the diffusion of tritium is closely related to that of lithium, so it is possible to find an indirect measure of the trend of tritium studying the diffusivity of Li+. In the present work, the synthesis of the Li4SiO4 is carried out by Spray drying followed by pyrolysis. The study of the Li+ ion diffusion on the sintered bodies, is investigated by means of electrical conductivity measurements. The effect of the gamma-ray irradiation is evaluated by the impedance spectroscopy method (EIS) from room temperature to 1173 K. The results indicate that the sintesis process employed can produce Li4SiO4 in the form of pebbles, finally the best ion species for the electrical conduction is the Li and is shown that the g-irradiation to a dose of 5MGy, facilitate its mobility through the creation of defects, without change in its conduction process. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:4431 / 4435
页数:5
相关论文
共 30 条
[1]  
Boukamp B.A., 1993, EQUIVCRT SOFTWARE
[2]   Overview of design and R&D of test blankets in Japan [J].
Enoeda, M ;
Akiba, M ;
Tanaka, S ;
Shimizu, A ;
Hasegawa, A ;
Konishi, S ;
Kimura, A ;
Kohyama, A ;
Sagara, A ;
Muroga, T .
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :415-424
[3]  
Fatma H., 2003, MATER CHEM PHYS, V77, P677
[4]   Low-temperature irradiation effects in lithium orthosilicates [J].
Feldbach, E. ;
Kotlov, A. ;
Kudryavtseva, I. ;
Liblik, P. ;
Lushchik, A. ;
Maaroos, A. ;
Martinson, I. ;
Nagirnyi, V. ;
Vasil'chenko, E. .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2006, 250 (1-2 SPEC. ISS.) :159-163
[5]   A finite element study on the grain boundary impedance of different microstructures [J].
Fleig, J ;
Maier, J .
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1998, 145 (06) :2081-2089
[6]   Blocking grain boundaries in yttria-doped and undoped ceria ceramics of high purity [J].
Guo, X ;
Sigle, W ;
Maier, J .
JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 2003, 86 (01) :77-87
[7]   Deuterium ion irradiation for tritium breeding material and evaluation for tritium inventories in test blanket module and blanket of a demonstration reactor [J].
Hino, T. ;
Shibata, H. ;
Yamauchi, Y. ;
Nobuta, Y. ;
Suzuki, S. ;
Akiba, M. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :713-717
[8]   PREPARATION AND PROPERTIES OF LITHIUM SILICATES AND ZIRCONATES CERAMIC BLANKET MATERIALS [J].
KAUKIS, AA ;
TILIKS, JE ;
TAMUZHS, VV ;
ABRAMENKOVS, AA ;
KIZANE, GK ;
UBELE, JA ;
VASILJEV, VG .
FUSION ENGINEERING AND DESIGN, 1991, 17 :13-16
[9]   CONDUCTIVITY MEASUREMENT AND EFFECT OF IMPURITY IONS DISSOLVED IN LI2O [J].
KONISHI, S ;
OHNO, H .
JOURNAL OF NUCLEAR MATERIALS, 1988, 152 (01) :9-13
[10]  
LEE J, 2003, J AM CERAM SOC, V77, P13