| LiAlO_2陶瓷小球的堆外放氚行为 |
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| 引用本文： | 肖成建,陈晓军,龚宇,黄洪文,冉光明,赵林杰,陈平,张勤英.LiAlO_2陶瓷小球的堆外放氚行为[J].强激光与粒子束,2015,27(1):016005. |
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| 作者姓名： | 肖成建 陈晓军 龚宇 黄洪文 冉光明 赵林杰 陈平 张勤英 |
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| 作者单位： | 1.中国工程物理研究院 核物理与化学研究所, 四川 绵阳 621 900 |
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| 基金项目： | 国家磁约束聚变能研究专项(2010GB112004, 2012GB106000, 2014GB111001) |
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| 摘 要： | 将LiAlO2陶瓷小球置于裂变反应堆中辐照,采用热解吸技术研究该类产氚材料的堆外放氚特性,考察了升温速率、载气组分、催化活性元素和提氚温度对氚释放行为的影响;采用电子自旋磁共振(ESR)实验技术研究了辐照缺陷的顺磁特征。结果表明:LiAlO2中氚的扩散速度慢,热解吸活化能高,氚释放主要分布在750~1000K;表面氢同位素交换反应贡献大,释氚形态受载气条件的影响较大,当氦气中添加H2时,会增大HTO转化成HT的比例;中子辐照会在LiAlO2中诱生F+,O-和O2-等缺陷色心,其退火湮灭行为与氚释放过程存在一定关系。
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| 关 键 词： | LiAlO2 氚增殖剂 放氚行为 氚燃料循环 聚变堆 |
| 收稿时间： | 2014/8/12 |
Out-of-pile tritium release of LiAlO2 pebble |
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| Affiliation: | 1.Institute of Nuclear Physics and Chemistry,CAEP,P.O.Box 919-212,Mianyang 621900,China |
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| Abstract: | It is important to understand the tritium properties of tritium breeding materials from the viewpoints of a fusion reactor blanket, the tritium fuel cycle and tritium safety. Out-of-pile tritium release experiments were performed to investigate the effects of heating rate, purge gas composition and platinum catalytic metal on the tritium release behaviors of the lithium aluminate (LiAlO2) ceramic pebbles after neutron-irradiation, and the ESR measuring technique was applied to analyzing the paramagnetic characteristics of irradiation defects. The experimental results show that the bred tritium requires a high temperature region of 750-1000 K to be liberated from LiAlO2 ceramic pebbles corresponding to the slow diffusivity and high desorption activity energy. Catalytic metals and hydrogen in the purge gas can enhance the hydrogen isotope exchange reaction between the tritium on the solid surface and the hydrogen in the purge gas, and accelerate the recovery rate of the molecular tritium (HT). Neutron irradiation can induce F+-center, O--center and O2- center in LiAlO2, and there is a certain relationship between the annihilation behavior of the irradiation defects and the tritium release process. |
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| Keywords: | LiAlO2 tritium breeder tritium release behavior tritium fuel cycle fusion reactor |
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