@misc{oai:repo.qst.go.jp:00072569,
 author = {Miyoshi, Yuuya and Aoki, Akira and Hiwatari, Ryoji and Sakamoto, Yoshiteru and Tobita, Kenji and 三善 悠矢 and 青木 晃 and 日渡 良爾 and 坂本 宜照 and 飛田 健次},
 month = {Sep},
 note = {The primary cooling water systems (CWS) of the blanket and the divertor is expected to have several amount of tritium because of permeation from the core plasma. In this research, the required performance of DEMO tritium removal facility to control the primary tritium concentration has been calculated and it is shown that existing devices can be applied to DEMO. The primary tritium is also expected to permeate the pipes to the secondary, thirdly CWS and finally, discharged into seawater. The evaluation of discharged tritium rate into seawater has been done. Because of tritium transport model from water to water is not well known, gas to gas calculation model is used. The results show that a heat exchanger decreases the tritium permeation rate by 1 order of magnitude, and H2 addition to the upstream cooling water also decreases the tritium permeation rate by 3 orders of magnitude., 13th International Symposium on Fusion Nuclear Technology},
 title = {Development of a plant system concept for a water-cooled fusion DEMO plant},
 year = {2017}
}