An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on the most comprehensive ex situ fuel retention data set on JET PFCs from the 2015-2016 ILW3 operating period is presented. The global fuel retention is 4.19 1023 D atoms, 0.19% of injected fuel. The inner divertor remains the region of highest fuel retention (46.5%). The T inventory in PFCs at the end of JET operations is calculated as 7.48 1022 atoms and is informative for accountancy, clean-up efficacy and waste liability assessments. The T accumulation rate at the upper inner divertor during JET DT operations has been used to assess the requirements and frequency of operation of a new laser ...
The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing compone...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...
An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuter...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
The evaluation of hydrogenic retention in present tokamaks is of crucial importance to estimate the ...
Future fusion reactors, like ITER, will rely on an active exhaust system to pump tritium (T) in the ...
The tritium balance based on pressure measurements in the divertor was performed for the DTE1 campai...
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) ...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main ch...
Understandings of tritium inventory in plasma facing materials are important issues for safe mainten...
The JET Task Force Fusion Technology (TF-FT) was launched in 2000 to use the unique capabilities, fa...
SIGLEAvailable from British Library Document Supply Centre- DSC:4672.2625(JET-R--94/11) / BLDSC - Br...
The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing compone...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...
An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuter...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
The evaluation of hydrogenic retention in present tokamaks is of crucial importance to estimate the ...
Future fusion reactors, like ITER, will rely on an active exhaust system to pump tritium (T) in the ...
The tritium balance based on pressure measurements in the divertor was performed for the DTE1 campai...
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) ...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main ch...
Understandings of tritium inventory in plasma facing materials are important issues for safe mainten...
The JET Task Force Fusion Technology (TF-FT) was launched in 2000 to use the unique capabilities, fa...
SIGLEAvailable from British Library Document Supply Centre- DSC:4672.2625(JET-R--94/11) / BLDSC - Br...
The phenomena of retention and de-trapping of deuterium (D) and tritium (T) in plasma facing compone...
Tritium retention analysis and tritium concentration measurement have been made during the large Tok...
The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step ...