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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles
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Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3-Li4SiO4 biphasic ceramic pebbles

机译：Li2TiO3中氚释放行为的比较和有前核 - 壳Li2tio3-Li4sio4双相陶瓷鹅卵石

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In a D-T fusion reactor, self-sufficiency of tritium is one of the critical issues to maintain steady-state operation of the reactor. Li2TiO3 and core-shell Li2TiO3-Li4SiO4 biphasic pebbles have been irradiated by thermal neutrons in Kyoto University. T-TDS (Tritium-Thermal Desorption Spectroscopy) was performed in Shizuoka University. There is one main tritium trapping site in neutron irradiated Li2TiO3. However, three tritium trapping sites are introduced in neutron irradiated core-shell Li2TiO3- Li4SiO4. The two peaks at lower temperature agree with that of Li2TiO3 which can be attributed to tritium release from Li2TiO3 including shell and core. The peak at higher temperature is mainly considered as tritium release from Li4SiO4. The amount of tritium released from core-shell Li2TiO3-Li4SiO4 is slight higher than that of Li2TiO3. The kinetic parameters of tritium diffusion in Li2TiO3 have been obtained. In the case of Li2TiO3 and core-shell Li2TiO3-Li4SiO4, almost all the tritium is released as HTO observed from T-TDS. Purge gas has little effect on tritium release, indicating tritium release from Li2TiO3 was mainly controlled by tritium diffusion in Li2TiO3 grain. (C) 2020 Elsevier B.V. All rights reserved.
机译：在D-T融合反应器中，氚的自给自足是保持反应器稳态操作的关键问题之一。 Li2TiO3和核心壳Li2TiO3-Li4SiO4双相卵石被京都大学的热中子照射。在静冈大学进行T-TDS（TRIIUM-热解吸光谱）。中子照射Li2TiO3有一个主要的氚捕获部位。然而，在中子辐照核 - 壳Li2TiO3-Li4SiO4中引入了三个氚捕获位点。在较低温度下的两个峰与Li2TiO3的峰值达成，其可归因于Li2TiO3的氚释放，包括壳和核。较高温度下的峰值主要被认为是Li4SiO4的氚释放。从核 - 壳Li2TiO3-Li4SiO4中释放的氚的量略高于Li2TiO3的少量。已经获得了Li2TiO3中氚扩散的动力学参数。在Li2TiO3和核心壳Li2TiO3-Li4SiO4的情况下，几乎所有氚被释放为从T-TDS观察到的HTO。净化气体对氚释放的影响几乎没有影响，表明来自Li2TiO3的氚释放主要是通过Li2TiO3晶粒中的氚扩散来控制。 （c）2020 Elsevier B.v.保留所有权利。

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