作者: K. Masaki , J. Yagyu , T. Arai , A. Kaminaga , K. Kodama
DOI: 10.13182/FST02-A235
关键词:
摘要: JT-60U has a variety of wall-conditioning methods such as baking the vacuum vessel, helium Taylor discharge cleaning, glow tokamak and boronization. Using these methods, high-power operation been successfully carried out with carbon-based first wall. The material behavior wall investigated, important knowledge was obtained on mechanical engineering plasma surface interactions. In order to understand tritium in JT-60U, retention exhausted through pumping system were measured. These results yield useful information future DT fusion machine.