Surface distribution of tritium on graphite tiles of divertor area in JT-60U

Fusion Science and Technology

Volumn 41, Issue 3 II, 2002, Pages 877-881

  Tanabe, T ^a   Miyasaka, K ^a   Sugiyama, K ^a   Masaki, K ^a   Kodama, K ^a   Miya, N ^a  

^a NAGOYA UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

GRAPHITE; IMAGE ANALYSIS; PLASMA THEORY; TILE;

PLASMA DISCHARGES;

TRITIUM;

EID: 0036576529     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst02-a22710     Document Type: Conference Paper

References (11)

1. In vessel trtium retention and removal in ITER
2. Tritium retention and clean-up in JET
3. Modeling of tritium retention in TFTR
4. Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation
5. Tritium depth profiles in graphite and carbon fibre composite material exposed to tokamak plasmas
6. Tritium detection in plasma facing component by imaging plate technique
7. Tritium detection in plasma facing components by imaging plate technique
8. Tritium retention in graphite inner wall of JT-60U
9. Appliation of imaging plate technique for determination of tritium distribution on graphite tiles of JT-60U
10. Temperature dependence of H saturation and isotope exchange