Tritium removal by laser heating and its application to tokamaks

Fusion Science and Technology

Volumn 41, Issue 3 II, 2002, Pages 716-720

  Skinner, C H ^a   Gentile, C A ^a   Guttadora, G ^a   Carpe, A ^a   Langish, S ^a   Young, K M ^a   Nishi, M ^a   Shu, W ^a  

^a PRINCETON PLASMA PHYSICS LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CARBON; CONTINUOUS WAVE LASERS; HEATING; LASER BEAM EFFECTS; NEODYMIUM LASERS; REMOVAL; THERMAL EFFECTS; TOKAMAK DEVICES;

LASER HEATING;

TRITIUM;

EID: 0036576616     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst02-a22680     Document Type: Conference Paper

References (16)

1. Assessment of erosion and tritium codeposition in ITER-FEAT
2. Modeling of tritium retention in TFTR
3. Tritium retention and clean-up in JET
4. Plasma-material interactions in current tokamaks and their implications for next-step fusion reactors
5. In-vessel tritium retention and removal in ITER-FEAT
6. In-situ detection and removal of carbon debris - A challenge for the next-step fusion device
7. Tritium experience in large tokamaks: Application to ITER
8. 2 laser heating
9. Tritium removal from codeposits on carbon tiles by a scanning laser
10. Characterization of deposition and erosion on the TFTR bumper limiter and wall
11. The PPPL differential atmospheric tritium sampler (DATS)
12. Oxygen removal of codeposited a-C:D layers from tokamak tiles
13. Behavior of developed radiation-resistant silica-core optical fibers under fission reactor irradiation