Measurement of the Radial Electric Field in the Plasma Edge of the Lithium Tokamak Experiment

The potential for magnetically confined fusion research to provide a clean, safe and abun- dant source of energy drives the proposed work. The experiment we aim to support and enhance, the Lithium Tokamak eXperiment (LTX) at the Princeton Plasma Physics Lab, has a unique configuration designed to study the key issues of transport and stability in fusion plasmas with non-recycling walls. It presently lacks critical diagnostics that are needed to investigate some of its most promising features. We propose to install a neutral beam based diagnostic on the LTX experiment to measure the electric field that is a fundamental quantity for understanding of plasma transport and stability. Electric field measurements in RF plasma chambers for plasm processing can improve the understanding and provide a technical edge to manufacturers in this huge and highly competitive industry. We plan to work with commercial companies to develop this as a diagnostic tool for improving plasma processing performance and efficiency.