Abstract
A baseline scenario of deuterium-tritium (D-T) plasma with peripheral high-field-side fuelling pellets has been produced in JET in order to mimic the situation in ITER. The isotope mix ratio is controlled in order to target the value of 50%-50% by a combination of tritium gas puffing and deuterium pellet injection. Multiple factors controlling the fuelling efficiency of individual pellets are analysed, with the following findings: (1) prompt particle losses due to pellet-triggered edge-localised modes (ELMs) are detected, (2) the plasmoid drift velocity might be smaller than that predicted by simulation, (3) post-pellet particle loss is controlled by transient phases with ELMs.The overall pellet particle flux normalised to the heat flux is similar to that in previous pellet fuelling experiments in AUG and JET.
| Original language | English |
|---|---|
| Article number | 076013 |
| Journal | Nuclear Fusion |
| Volume | 64 |
| Issue number | 7 |
| DOIs | |
| Publication status | Published - Jul 2024 |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
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SDG 7 Affordable and Clean Energy
OECD Field of Science
- 1.3 Physical Sciences
Keywords
- JET deuterium-tritium plasma
- particle losses
- pellets
- tokamak
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