The objectives of NSTX-U research are to reinforce the advantages of STs while addressing
the challenges. To extend confinement physics of low-A, high beta plasmas to lower …

The lithium vapor box divertor is a proposed divertor design that will minimize contamination
of the upstream plasma in a fusion device, while also ensuring protection of the target. In this …

One of the most critical challenges for future fusion reactors is to develop longevity plasma-
facing components (PFCs) exposed to extremely high heat and neutron loads. As opposed …

As fusion devices push to become more compact, economical, and high performance, one
potentially enabling technology is liquid lithium-based plasma-facing components (LL …

Numerical analysis provides the design choice and operating window of liquid metal Plasma
Facing Components (PFC) concepts. Coupled analysis of boundary plasma together with …

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 …

Commercial fusion reactors will be faced with extremely high divertor target heat fluxes that
will require mitigation. Simulations of detachment in an NSTX-U scenario projected to have …

A liquid lithium divertor can improve performance of future fusion devices by creating
efficient power exhaust and improving the energy confinement via pum** of the hydrogen …

Liquid metal (LM) on plasma-facing components (PFCs) creates a renewable protective
cover enhancing power exhaust and protecting the solid substrate. Additionally, energy …

Both scientific and technical innovation is needed for the realization of an attractive
engineering solution for a timely and cost-effective Pilot Plant, the design and construction of …