@article{oai:repo.qst.go.jp:00049550, author = {三善, 悠矢 and 青木, 晃 and 日渡, 良爾 and 坂本, 宜照 and 飛田, 健次 and Joint, Special Design Team for DEMO The and 三善 悠矢 and 日渡 良爾 and 坂本 宜照 and 飛田 健次}, issue = {B}, journal = {Fusion Engineering and Design}, month = {Feb}, note = {The primary cooling water systems (CWS) of the blanket and the divertor is anticipated 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 anticipated to permeate the pipes to the downstream CWS and turbine system. Finally, tritium in turbine system permeates a condenser pipes and is leaked into seawater. The evaluation of tritium leakage 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.}, pages = {1577--1580}, title = {Evaluation of tritium leakage rate into seawater in fusion DEMO cooling water system}, volume = {136}, year = {2019} }