@article{oai:repo.qst.go.jp:00048884,
 author = {片山, 一成 and 染谷, 洋二 and 飛田, 健次 and 中村, 博文 and 谷川, 尚 and 中村, 誠 and 朝倉, 伸幸 and 星野, 一生 and 近田, 拓未 and 波多野, 雄治 and 深田, 智 and 染谷 洋二 and 飛田 健次 and 中村 博文 and 谷川 尚 and 中村 誠 and 朝倉 伸幸 and 星野 一生},
 journal = {Fusion Science and Technology},
 month = {May},
 note = {The approximate estimation of tritium permeation rate under the acceptable assumption from a safety point of view is surely useful to progress the design activities for a fusion DEMO reactor. Tritium permeation rates in the blanket and the divertor were estimated by the simplified evaluation model under the recent DEMO conditions in the water-cooled blanket with solid breeder as a first step. Plasma driven permeation rates in tungsten wall were calculated by applying Doyle & Brice model and gas driven permeation rates in F82H were calculated for hydrogen-tritium two component system. In the representative recent DEMO condition, the following tritium permeation rates were obtained, 1.8 g/day in the blanket first wall, 2.3 g/day in the blanket tritium breeding region and 1.6 g/day in the divertor. Total tritium permeation rate into the cooling water was estimated to be 5.7 g/day.},
 pages = {261--267},
 title = {Estimation of Tritium Permeation Rate to Cooling Water in Fusion DEMO Condition},
 volume = {71},
 year = {2018}
}