Basic study for fuel recovery in divertor of nuclear fusion by using titanium

S. Togawa, Fumitaka Ishikawa, Saori Mera, A. Tonegawa, M. Amano, Y. Matsumura
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Abstract

Nuclear fusion device is developed as one of the future energy source. Fuels particles (tritium and deuterium), which don’t react, are exhausted from divertor to the outside of the reactor with a pump. Since tritium is a radioisotope and rarely exists in nature, fuels recovery is necessary. In this study, we have developed a new recover method by hydrogen storage material in the divertor plate. Tungsten is a candidate material for ITER as well as other future magnetic fusion energy devices. The recovery material consists of tungsten which is combined with titanium films as a hydrogen storage material. The titanium films were deposited by ion plating on tungsten substrates. The sample surface temperature was measured by radiation thermometer. After irradiation with deuterium plasma, retention properties of deuterium were examined with thermal desorption spectroscopy (TDS). The experimental results indicated that this method can be applied as a new hydrogen fuel recovery.
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利用钛回收核聚变分流器燃料的基础研究
核聚变装置是未来能源发展的方向之一。不发生反应的燃料颗粒(氚和氘)通过泵从导流器排出到反应堆外部。由于氚是一种放射性同位素,在自然界中很少存在,所以燃料回收是必要的。在本研究中,我们开发了一种新的利用导流板储氢材料的回收方法。钨是ITER以及其他未来磁聚变能装置的候选材料。回收材料由钨组成,钨与钛膜结合作为储氢材料。采用离子镀法制备钛薄膜。用辐射温度计测量样品表面温度。用热解吸光谱(TDS)研究了氘等离子体辐照后氘的保留特性。实验结果表明,该方法可作为一种新型的氢燃料回收方法。
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