The reversed field pinch

L Marrelli, P Martin, ME Puiatti, JS Sarff… - Nuclear …, 2021 - iopscience.iop.org
This paper reviews the research on the reversed field pinch (RFP) in the last three decades.
Substantial experimental and theoretical progress and transformational changes have been …

An overview of lithium experiments on HT-7 and EAST during 2012

JS Hu, J Ren, Z Sun, GZ Zuo, QX Yang, JG Li… - Fusion Engineering and …, 2014 - Elsevier
In 2012, lithium coating with an upgraded system on EAST, the first application of lithium
granules injection for ELMs pacing on EAST, and the first flowing lithium limiter experiments …

Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623 K

XC Meng, L Li, CL Li, D Andruczyk, K Tritz, R Maingi… - Corrosion …, 2022 - Elsevier
In this study, the corrosion behaviours of molybdenum (Mo) and a Mo-based alloy (TZM)
were investigated using a static immersion corrosion technique. Weight loss, surface …

Study of the corrosion characteristics of 304 and 316L stainless steel in the static liquid lithium

DH Zhang, XC Meng, GZ Zuo, M Huang, L Li… - Journal of Nuclear …, 2021 - Elsevier
Liquid lithium (Li) is considered as the tritium breeder as well as a potential blanket coolant
and/or plasma-facing material (PFM) in fusion devices, while steels are widely used as an …

FTU results with a liquid lithium limiter

G Mazzitelli, ML Apicella, D Frigione… - Nuclear …, 2011 - iopscience.iop.org
Since the end of 2005 most of the plasma–wall interaction experiments on FTU have been
focused on the possible use of liquid lithium as the plasma facing material. Liquid lithium …

Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST

GZ Zuo, JS Hu, R Maingi, Z Sun, QX Yang… - Nuclear …, 2018 - iopscience.iop.org
Significant engineering and physic progress was made by the upgrade of a flowing liquid
lithium limiter (FLiLi) inserted into EAST H-mode discharges in 2016. The progress includes …

Protection of tokamak plasma facing components by a capillary porous system with lithium

I Lyublinski, A Vertkov, S Mirnov, V Lazarev - Journal of Nuclear Materials, 2015 - Elsevier
Abstract Development of plasma facing material (PFM) based on the Capillary-Porous
System (CPS) with lithium and activity on realization of lithium application strategy are …

Liquid lithium surface control and its effect on plasma performance in the HT-7 tokamak

GZ Zuo, J Ren, JS Hu, Z Sun, QX Yang, JG Li… - Fusion Engineering and …, 2014 - Elsevier
Experiments with liquid lithium limiters (LLLs) have been successfully performed in HT-7
since 2009 and the effects of different limiter surface structures on the ejection of Li droplets …

[HTML][HTML] Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes

TW Morgan, A Vertkov, K Bystrov, I Lyublinski… - Nuclear Materials and …, 2017 - Elsevier
Liquid metal infused capillary porous structures (CPSs) are considered as a potential
divertor solution for DEMO due to their potential power handling capability and resilience to …

Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development

M Ono, MA Jaworski, R Kaita, HW Kugel, JW Ahn… - Nuclear …, 2013 - iopscience.iop.org
Developing a reactor-compatible divertor has been identified as a particularly challenging
technology problem for magnetic confinement fusion. Application of lithium (Li) in NSTX …