Lithium Tokamak Experiment

The Lithium Tokamak Experiment (LTX), and its predecessor, the Current Drive Experiment-Upgrade (CDX-U), are devices dedicated to the study of liquid lithium as a plasma-facing component (PFC) at Princeton Plasma Physics Laboratory. The Lithium Tokamak Experiment (LTX), and its predecessor, the Current Drive Experiment-Upgrade (CDX-U), are devices dedicated to the study of liquid lithium as a plasma-facing component (PFC) at Princeton Plasma Physics Laboratory. One of the ongoing research issues for commercial fusion power development is the choice of material for the plasma-facing portions of the reactor vessel, also known as the first wall. Most reactors operate at the equivalent of a high vacuum and thus demand high-strength materials to resists the inward pressure of the magnets against the empty interior. Typical materials are those used in other chemical and atomic processes, like various steel alloys. Unfortunately, these same materials have a number of disadvantages when used in fusion reactors. One major problem is that when escaped fusion fuel hits the material it cools, returning to the fuel mass at a lower temperature and cooling the fuel as a whole. This is known as 'recycling'. The other is that these reactions can also spall off metal atoms, and due to their high atomic mass, or 'high-Z', when they are heated they give off copious amounts of X-rays which also cools the plasma fuel. One of the attractive features of a liquid lithium PFC is that it virtually eliminates recycling. This is because lithium has a high chemical reactivity with atomic hydrogen, which is then retained in the PFC. In addition, lithium has a low atomic number, Z. This gives the lowest possible energy loss by radiation from PFC material that may end up in the plasma, because radiation increases strongly with increasing Z. Finally, flowing liquid lithium can also potentially handle the high power densities expected on reactor walls. All major tokamaks have obtained their best performance under low recycling conditions. If a fully non-recycling wall can be achieved, theory predicts that the basic nature of magnetic confinement will be changed. The temperature and density profiles, and plasma current distributions, would potentially eliminate deleterious plasma instabilities. Furthermore, the transport mechanisms causing the loss of energy and particles would be reduced, and plasmas with higher energy confinement could result. Operated at PPPL from 2000 to 2005. As the first test of large area liquid lithium PFC, CDX-U had a toroidal tray on the bottom of the vacuum chamber to contain the lithium. Even with this partial non-recycling PFC, major improvements in plasma performance were obtained. Impurities were reduced, and a dramatic improvement (x6) in energy confinement was observed in 2005.