The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with members of the Japan Atomic Energy Research Institute (JAERI), Tritium Engineering Laboratory have commenced in-situ tritium measurements of the TFTR bumper limiter. The Tokamak Fusion Test Reactor (TFTR) operated with tritium from 1993 to 1997. During this time {approximately} 53,000 Ci of tritium was injected into the TFTR vacuum vessel. After the cessation of TFTR plasma operations in April 1997 an aggressive tritium cleanup campaign lasting {approximately} 3 months was initiated. The TFTR vacuum vessel was subjected to a regimen of glow discharge cleaning (GDC) and dry nitrogen and ''moist air'' purges. Currently {approximately} 7,500 Ci ...
Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 year...
The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Te...
Understandings of tritium inventory in plasma facing materials are important issues for safe mainten...
The tritium surface distribution on graphite tiles used in the Tokamak Fusion Test Reactor (TFTR) bu...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Recent experiments on the Tokamak Fusion Test Reactor (TFTR) have afforded an opportunity to measure...
A simple tritium cleanup experiment was carried out in TFTR following the initial high power deuteri...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. ...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
Tritium issues will play a central role in the performance and operation of next-step deuterium-trit...
TFTR Tritium Stack and Area Monitoring Systems have been developed to provide the required level of ...
The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been meas...
Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 year...
The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Te...
Understandings of tritium inventory in plasma facing materials are important issues for safe mainten...
The tritium surface distribution on graphite tiles used in the Tokamak Fusion Test Reactor (TFTR) bu...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Recent experiments on the Tokamak Fusion Test Reactor (TFTR) have afforded an opportunity to measure...
A simple tritium cleanup experiment was carried out in TFTR following the initial high power deuteri...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. ...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
Tritium issues will play a central role in the performance and operation of next-step deuterium-trit...
TFTR Tritium Stack and Area Monitoring Systems have been developed to provide the required level of ...
The areal distribution of tritium retention in tiles from TEXTOR, TFTR, JT-60U and JET has been meas...
Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 year...
The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Te...
Understandings of tritium inventory in plasma facing materials are important issues for safe mainten...