A simple tritium cleanup experiment was carried out in TFTR following the initial high power deuterium-tritium discharges in December 1993. A series of 34 ohmic and deuterium neutral beam fueled shots was used to study the removal of tritium implanted into the wall and limiters. A very large plasma was created in each discharge to ``scrub`` an area as large as possible. Beam-fueled shots at 2.5 to 7.5 MW of injected power were used to monitor tritium concentration levels in the plasma by detection of DT-neutrons. The neutron signal decreased by a factor of 4 during the experiment, remaining well above the expected T-burnup level. The amount of tritium recovered at the end of the cleanup was about 8% of the amount previously injected with hi...
TFTR Tritium Stack and Area Monitoring Systems have been developed to provide the required level of ...
TFTR has begun its campaign to study deuterium-tritium fusion under reactor-like conditions. Variabl...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...
Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. ...
Recent experiments on the Tokamak Fusion Test Reactor (TFTR) have afforded an opportunity to measure...
The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with ...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) ...
In late 1993 the Tokamak Fusion Test Reactor began operating with a deuterium-tritium (DT) fuel mixt...
Tritium and deuterium are expected to be the fuel for the first fusion power reactors. Being radioac...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 year...
In the summer/fall of 1996 after nearly three years of D-T operations, TFTR underwent an extended ou...
The paper describes a series of experiments in the Joint European Torus (JET), culminating in the fi...
The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Te...
TFTR Tritium Stack and Area Monitoring Systems have been developed to provide the required level of ...
TFTR has begun its campaign to study deuterium-tritium fusion under reactor-like conditions. Variabl...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...
Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. ...
Recent experiments on the Tokamak Fusion Test Reactor (TFTR) have afforded an opportunity to measure...
The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with ...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) ...
In late 1993 the Tokamak Fusion Test Reactor began operating with a deuterium-tritium (DT) fuel mixt...
Tritium and deuterium are expected to be the fuel for the first fusion power reactors. Being radioac...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 year...
In the summer/fall of 1996 after nearly three years of D-T operations, TFTR underwent an extended ou...
The paper describes a series of experiments in the Joint European Torus (JET), culminating in the fi...
The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Te...
TFTR Tritium Stack and Area Monitoring Systems have been developed to provide the required level of ...
TFTR has begun its campaign to study deuterium-tritium fusion under reactor-like conditions. Variabl...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...