S. Togawa, Fumitaka Ishikawa, Saori Mera, A. Tonegawa, M. Amano, Y. Matsumura
{"title":"Basic study for fuel recovery in divertor of nuclear fusion by using titanium","authors":"S. Togawa, Fumitaka Ishikawa, Saori Mera, A. Tonegawa, M. Amano, Y. Matsumura","doi":"10.2978/jsas.11004","DOIUrl":null,"url":null,"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.","PeriodicalId":14991,"journal":{"name":"Journal of Advanced Science","volume":"28 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2016-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Advanced Science","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.2978/jsas.11004","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0
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.