Author/Authors :
Sugiyama، نويسنده , , K and Tanabe، نويسنده , , T and Miyasaka، نويسنده , , K and Masaki، نويسنده , , K and Tobita، نويسنده , , K and Miya، نويسنده , , N and Philipps، نويسنده , , V and Rubel، نويسنده , , M and Skinner، نويسنده , , C.H. and Gentile، نويسنده , , C.A and Saze، نويسنده , , T and Nishizawa، نويسنده , , K، نويسنده ,
Abstract :
We have investigated the tritium depth profile near the surface of the limiter/divertor tiles used in the deuterium fueled machines, such as TEXTOR, TFTR and JT-60U by means of the imaging plate technique and a tritium survey monitor. Tritium depth profiles near the surface of the sample tiles were estimated by comparing the experimental results to a calculation using a 3-D Monte-Carlo code. In every sample tile, there was little tritium in the range from the surface to 1 μm depth. In contrast, tritium density tended to increase beyond 1 μm depth. These results indicate that the tritium retained near the surface was easily removed by isotope exchange with a deuterium plasma or various other tritium removal operations. On the other hand, such operations did not remove tritium retained beyond 1 μm depth, and this could be a potential issue in a next D–T machine.
