Lithium, a path to make fusion energy affordable
A De Castro, C Moynihan, S Stemmley, M Szott… - Physics of …, 2021 - pubs.aip.org
In this tutorial article, we review the technological, physics, and economic basis for a
magnetic fusion device utilizing a flowing liquid lithium divertor (molten metal velocity in the …
magnetic fusion device utilizing a flowing liquid lithium divertor (molten metal velocity in the …
Improved neutral and plasma density control with increasing lithium wall coatings in the Lithium Tokamak Experiment-β (LTX-β)
A comparison of three sets of Lithium Tokamak Experiment-β (LTX-β) discharges is
presented, each with progressively more lithium evaporatively deposited on the stainless …
presented, each with progressively more lithium evaporatively deposited on the stainless …
Extending the low-recycling, flat temperature profile regime in the lithium tokamak experiment-β (LTX-β) with ohmic and neutral beam heating
DP Boyle, J Anderson, S Banerjee, RE Bell… - Nuclear …, 2023 - iopscience.iop.org
Recent experiments in the lithium tokamak experiment-β (LTX-β) have extended the
duration, performance, operating conditions, and diagnosis of the flat-temperature profile …
duration, performance, operating conditions, and diagnosis of the flat-temperature profile …
Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST
K Hanada, N Yoshida, M Hasegawa, M Oya… - Nuclear Materials and …, 2021 - Elsevier
QUEST (Q-shu university experiment with steady state spherical tokamak) is a midsize
spherical tokamak capable of steady-state operation, comprising all-metal plasma-facing …
spherical tokamak capable of steady-state operation, comprising all-metal plasma-facing …
Plasma Facing Component Characterization and Correlation With Plasma Conditions in Lithium Tokamak Experiment-β
A Maan, E Ostrowski, R Kaita… - … on Plasma Science, 2020 - ieeexplore.ieee.org
Lithium coatings in the Lithium Tokamak eXperiment (LTX) led to flat temperature profiles.
The flat temperature profiles were observed along with a hot, low density edge, implying a …
The flat temperature profiles were observed along with a hot, low density edge, implying a …
SIMS and HR-XPS characterization of lithiated graphite from the magnetic fusion device RFX-mod
B Rais, ET Ostrowski, A Canton, CH Skinner… - Applied Surface …, 2021 - Elsevier
Lithium wall conditioning has improved the performance of many magnetic fusion devices. Li
conditioning in the RFX-mod device was performed by:(1) a single Li pellet injector and (2) a …
conditioning in the RFX-mod device was performed by:(1) a single Li pellet injector and (2) a …
Detailed studies of the processes in low energy H irradiation of Li and Li-compound surfaces
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 …
and chemistry modeling of plasma–material interfaces in the tokamak fusion plasma edges …
Oxidation of lithium plasma facing components and its effect on plasma performance in the lithium tokamak experiment-β
A Maan, DP Boyle, R Kaita, ET Ostrowski… - Plasma Physics and …, 2020 - iopscience.iop.org
The characteristics of lithium-coated plasma-facing components (PFCs) have been
correlated with plasma performance on the lithium tokamak experiment-β (LTX-β). Previous …
correlated with plasma performance on the lithium tokamak experiment-β (LTX-β). Previous …
Neutral beam prompt loss in LTX-β
W Capecchi, JK Anderson, DP Boyle, PE Hughes… - Nuclear …, 2021 - iopscience.iop.org
Prompt loss of beam injected fast ions approaches 100% in lithium tokamak experiment-
beta (LTX-β) discharges, though significantly improved confinement is expected for the …
beta (LTX-β) discharges, though significantly improved confinement is expected for the …
Toroidal plasma acceleration due to NBI fast ion losses in LTX-β
PE Hughes, W Capecchi, DB Elliott… - Plasma Physics and …, 2021 - iopscience.iop.org
Abstract The recent Lithium Tokamak Experiment-Beta (LTX-β) upgrade includes the
addition of neutral beam injection (NBI) in the same direction as the plasma current (co-I P) …
addition of neutral beam injection (NBI) in the same direction as the plasma current (co-I P) …