A study of surface pretreatment of tritium-getter alloy for enhancement of insensitiveness to impurities

氚吸气合金表面预处理增强杂质不敏感性的研究

基本信息

批准号：
10680473
负责人：
FUKADA Satoshi
金额：
$ 2.11万
依托单位：
KYUSHU UNIVERSITY
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (C)
财政年份：
1998
资助国家：
日本
起止时间：
1998 至 1999
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-10680473/
关键词：
tritium zirconium alloy fusion fuel cycle alkali pretreatment water vapor cracking methane cracking impurity hydrogen storage Zr_2Fe Zn(Mni-xFex)_2 燃料精製システム不純物被素水素貯蔵合金

项目摘要

Some zirconium-alloy getters are expected to be used for tritium separation, purification and storage in a fuel cycle of a nuclear fusion reactor. We have been investigated particle beds of Zr, ZrCo, ZrNi and ZrィイD22ィエD2Fe which can recover the tritium concentration in gas streams lower than the maximum permissible level for the radioisotope in Japan. However, once tritium-getters contact with any of the gaseous impurities such as OィイD22ィエD2, HィイD22ィエD2O and CO, they lose most of their hydrogen capacities. Based on our previous experimental studies on mass-transfer processes in alloy beds, new surface pretreatment techniques in order to enhance insensitiveness to impurities were tested with their keeping the high absorption capacity. The three surface pretreatment techniques are (1) alkali pretreatment, (2) pd depositing (3) Cu depositing. In 1998 we comparatively investigated the surface pretreatment to the ZrィイD22ィエD2Fe getter, and its hydrogenating rate after the alkali pretreatment was enhanced about ten times faster than that of the non-treated getter. It was found that pretreated ZrィイD22ィエD2Fe particles under the room temperature can absorb tritium less than the detection limit. In 1999, methane and tritium water vapor cracking by a Zr(MnィイD20.5ィエD2FeィイD20.5ィエD2)ィイD22ィエD2 bed was experimentally investigated. Methane at higher than 650ィイD1゜ィエD1C and water vapor at 350ィイD1゜ィエD1C were successfully cracked by the Zr(MnィイD20.5ィエD2FeィイD20.5ィエD2)ィイD22ィエD2 bed. Results obtained in the present study have been presented at the international symposium of the fusion nuclear technology and that of the hydrogen energy and have been also reported to international journals.

预计某些锆合金获取器将用于核融合反应器的燃料周期中的trium分离，纯化和储存。我们已经研究了ZR，ZRCO，ZRNI和ZRII D2FE的粒子床，这些粒子可以恢复低于日本放射性分析的最大允许水平的tri浓浓度。然而，一旦trium-getters与任何气态杂质（例如OI D22，H22E D2O和CO）接触，它们就会失去大部分氢能力。基于我们以前关于合金床中质量转移过程的实验研究，为了增强对杂质不敏感性的新表面预处理技术，通过保持高苦难能力进行了测试。三种表面预处理技术是（1）碱预处理，（2）PD沉积（3）Cu沉积。在1998年，我们比较研究了ZR D22E D2FE Getter的表面预处理，其碱性预处理后其氢化速率的增强速度比未经处理的Getter快十倍。发现在室温下预处理的ZR D22E D2FE颗粒可以吸收小于检测极限。在1999年，通过ZR（MN D20.5E D2FE D20.5E D2）II D22E D2床进行了甲烷和tri剂水蒸气裂纹。 ZR（MNI D20.5 D2FE D20.5 D2）D22床成功破解了高于650 d1c的甲烷和350 d1c时的水蒸气。在本研究中获得的结果已在融合核技术的国际研讨会和氢能的国际研讨会上提出，并已报告给国际期刊。