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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.

一些锆合金吸气剂有望用于核聚变反应堆燃料循环中的氚分离、纯化和储存。我们已经研究了Zr、ZrCo、ZrNi和Zr D22 D2 Fe的颗粒床，它们可以回收低于日本放射性同位素最大允许水平的气流中的氚浓度。然而，一旦氚吸气剂与任何气体杂质如O-2 H2O-D22-D2 O和CO接触，它们就会失去大部分的氢容量。在前期合金床传质过程实验研究的基础上，在保持高吸附容量的前提下，研究了新的表面预处理技术，以提高合金床对杂质的不敏感性。三种表面预处理技术是（1）碱预处理，（2）钯沉积，（3）铜沉积。1998年我们对锆英石D22型铁基吸气剂进行了表面预处理的对比研究，发现经过碱预处理后，其氢化速率比未经处理的吸气剂提高了10倍左右。结果表明，经预处理的Zr_（12）D_22 Fe_（12）Fe_（12）颗粒在室温下对氚的吸附量小于检测限。1999年，在Zr（Mn ↓ [2] O ↓ [2] D ↓ [20.5] O ↓ [2] Fe ↓ [2] D ↓ [20.5] O ↓ [2]）↓ [2] O ↓ [2] D ↓ [2]床上进行了甲烷和氚水蒸汽裂解的实验研究。在Zr（Mn）20.5 Mn 20.5 Fe 20.本研究所获得的结果已在聚变核技术和氢能国际研讨会上发表，并已在国际期刊上发表。