In the operation of tokamak such as ITER, it is important to understand the behavior of hydrogen isotopes and other elements in vacuum vessel for tritium inventory control and design of the plasma exhaust process. Particularly removal of carbon-tritium codeposited layer is considered as a crucial issue for ITER, because of its suspected tritium inventory. In JT-60U, exhaust gas was analyzed in the operation of discharge cleaning and tokamak discharge experiments, and the behavior of hydrogen isotopes and carbon were investigated. In discharge cleaning experiments, the degassing rate of hydrogen isotopes in GDC (glow discharge cleaning) was much larger than that in TDC (Taylor discharge cleaning) and ECRDC (electron cyclotron resonance discharge cleaning). Exhausted hydrocarbons were far less than hydrogen. During tokamak discharge experiments, various carbon compounds such as CD4, C2D2, C2D4, C2D6 and CO2 were detected. The maximum amount of exhausted carbon was several mg for each shot. There was a strong correlation between exhausted hydrocarbon and tritium. The exhausted hydrocarbon increased with the wall temperature
[1]
M. Nishi,et al.
Application of glow discharges for tritium removal from JT-60U vacuum vessel
,
2004
.
[2]
H. Nakamura,et al.
Analysis of exhausted gas in JT-60 deuterium operation
,
2003,
20th IEEE/NPSS Symposium onFusion Engineering, 2003..
[3]
C. Skinner,et al.
Tritium retention of plasma facing components in tokamaks
,
2003
.
[4]
H. Takenaga,et al.
Measurement of the chemical sputtering yields of CH4/CD4 and C2Hx/C2Dx at the carbon divertor plates of JT-60U
,
2002
.
[5]
C. H. Skinner,et al.
Plasma-material interactions in current tokamaks and their implications for next step fusion reactors
,
2001
.