A method for visually observing tritium deposition on the surface of the Tokamak Fusion Test Reactor (TFTR) deuterium-tritium (D-T) tiles is being investigated at the Princeton Plasma Physics Laboratory. A green phosphor (P31, zinc sulfide: copper) similar to that used in oscilloscope screens with a wavelength peak of 530 nm was positioned on the surface of a TFTR D-T tile. The approximately 600 gram tile, which contains approximately 1.5 Ci of tritium located on the top approximately 1-50 microns of the surface, was placed in a two liter lexan chamber at Standard Temperature and Pressure (STP). The phosphor plates and phosphor powder were placed on the surface of the tile which resulted in visible light being observed, the consequence of t...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
Tritium accumulation in fusion reactor materials is considered a serious radiological issue, therefo...
Tritium (T) distributions on the plasma-facing surfaces (PFSs) and inside castellation of Be limiter...
A imaging detector has been developed for the purpose of providing a non-destructive, real time meth...
The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with ...
The tritium surface distribution on graphite tiles used in the Tokamak Fusion Test Reactor (TFTR) bu...
Princeton Plasma Physics Laboratory (PPPL) has developed a method of imaging tritium on in-situ surf...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
The objective of this Plant Directed Research and Demonstration (PDRD) task was to develop a system ...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
Tritium distributions on the W-coated divertor tiles used with Be wall in JET 2011-2012 ITER-like wa...
A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbo...
Three potential methods for evaluating the surface tritium content of the TFTR vacuum vessel are des...
Three potential methods for measuring the surface tritium content of the TFTR vacuum vessel are desc...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
Tritium accumulation in fusion reactor materials is considered a serious radiological issue, therefo...
Tritium (T) distributions on the plasma-facing surfaces (PFSs) and inside castellation of Be limiter...
A imaging detector has been developed for the purpose of providing a non-destructive, real time meth...
The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with ...
The tritium surface distribution on graphite tiles used in the Tokamak Fusion Test Reactor (TFTR) bu...
Princeton Plasma Physics Laboratory (PPPL) has developed a method of imaging tritium on in-situ surf...
The tritium profiles in a TFTR graphite tile exposed to D-D plasmas and in a JET graphite tile emplo...
Tritium analysis has carried out for the 4D C-C composite deposition probe exposed to the edge of D-...
The objective of this Plant Directed Research and Demonstration (PDRD) task was to develop a system ...
A novel laser heating technique has recently been applied to removing tritium from carbon tiles that...
Tritium distributions on the W-coated divertor tiles used with Be wall in JET 2011-2012 ITER-like wa...
A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbo...
Three potential methods for evaluating the surface tritium content of the TFTR vacuum vessel are des...
Three potential methods for measuring the surface tritium content of the TFTR vacuum vessel are desc...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
Tritium accumulation in fusion reactor materials is considered a serious radiological issue, therefo...
Tritium (T) distributions on the plasma-facing surfaces (PFSs) and inside castellation of Be limiter...