The SOLPS-ITER code is utilized to analyze the boundary plasma associated with a fast-
flow lithium (Li) divertor configuration in the fusion nuclear science facility (FNSF) tokamak …

Strong poloidal refueling asymmetry in the DIII-D tokamak is inferred from line radiation
measurements. Synthetic diagnostics in neutral transport modeling coupled to gyrokinetic …

We report the first observation of global recycling coefficient R near 0.5 in the Lithium
Tokamak eXperiment-β (LTX-β), significantly below the minimum R previously reported in …

Recent experiments in the lithium tokamak experiment-β (LTX-β) have extended the
duration, performance, operating conditions, and diagnosis of the flat-temperature profile …

We have used a combination of pico-to-nano temporal/spatial scale computational physics
and chemistry modeling of plasma–material interfaces in the tokamak fusion plasma edges …

We present observations, numerical simulations, and analysis from experiments in the
Lithium Tokamak Experiment-Beta (LTX-β) in which the electron temperature profile (T e (r)) …

We observed enhanced net lithium deposition and lithium erosion, possibly dominated by
physical sputtering of lithium by lithium-ion bombardment, on the outer plasma-facing …

We have investigated, using molecular dynamics, the surface chemistry of hydrogen incident
on the amorphous and crystalline lithium oxide and lithium hydroxide surfaces upon being …

The paper provides a brief overview of research activity related to the use of the flowing
liquid lithium as a plasma facing material of the limiter and divertor in tokamaks. A …

An edge Lyman-alpha-based beam emission spectroscopy (LyBES) diagnostic, using a
heating NBI (neutral beam injection) system, is currently under development on the HL-2A …