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Title: Magnetohydrodynamics in free surface liquid metal flow relevant to plasma-facing components

Journal Article · · Nuclear Fusion

Abstract While flowing Liquid Metal (LM) Plasma-Facing Components (PFCs) represent a potentially transformative technology to enable long-pulse operation with high-power exhaust for fusion reactors, Magnetohydrodynamic (MHD) drag in the conducting LM will reduce the flow speed. Experiments have been completed in the linear open-channel LMX-U device [Hvasta et al 2018 Nucl. Fusion   58 01602] for validation of MHD drag calculations with either insulating or conducting walls, with codes similar to those used to design flowing LM PFCs for a Fusion Nuclear Science Facility [Kessel et al 2019 Fusion Sci. Technol . 75 886]. We observe that the average channel flow speed decreased with the use of conducting walls and the strength of the applied transverse magnetic field. The MHD drag from the retarding Lorentz force resulted in an increase of the LM depth in the channel that ‘piled up’ near the inlet, but not the outlet. As reproduced by OpenFOAM and ANSYS CFX calculations, the magnitude and characteristics of the pileup in the flow direction increased with the applied traverse magnetic field by up to 120%, as compared to the case without an applied magnetic field, corresponding to an average velocity reduction of ∼45%. Particle tracking measurements confirmed a predicted shear in the flow speed, with the surface velocity increasing by 300%, despite the 45% drop in the average bulk speed. The MHD effect makes the bulk flow laminarized but keeps surface waves aligned along the magnetic field lines due to the anisotropy of MHD drag. The 3D fringe field and high surface velocity generate ripples around the outlet region. It was also confirmed that the MHD drag strongly depends on the conductivity of the channel walls, magnetic field, and volumetric flow rate, in agreement with the simulations and a developed analytical model. These validated models are now available to begin to determine the conditions under which the ideal LM channel design of a constant flow speed and fluid depth could be attained.

Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program
Grant/Contract Number:
AC02-09CH11466; FWP 1019
OSTI ID:
1984325
Alternate ID(s):
OSTI ID: 1975171; OSTI ID: 1986327
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Vol. 63 Journal Issue: 7; ISSN 0029-5515
Publisher:
IOP PublishingCopyright Statement
Country of Publication:
IAEA
Language:
English

References (48)

Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility journal June 2019
Perspectives for the liquid lithium and tin targets in the Italian Divertor Test Tokamak (I-DTT) divertor journal September 2019
Numerical Analysis of 2-D and 3-D MHD Flows Relevant to Fusion Applications journal September 2017
Divertorlets concept for low-recycling fusion reactor divertor: experimental, analytical and numerical verification journal June 2022
On a burning plasma low recycling regime with P DT = 23–26 MW, Q DT = 5–7 in a JET-like tokamak journal July 2019
Li-CPS limiter in tokamak T-11M journal April 2003
Demonstrating electromagnetic control of free-surface, liquid-metal flows relevant to fusion reactors journal November 2017
Study on measurement of the flow velocity of liquid lithium jet using MHD effect for IFMIF journal November 2018
FTU results with a liquid lithium limiter journal May 2011
Experimental demonstration of hydraulic jump control in liquid metal channel flow using Lorentz force journal June 2018
Performance of liquid-lithium-filled 3D-printed tungsten divertor targets under deuterium loading with ELM-like pulses in Magnum-PSI journal May 2021
On the exploration of innovative concepts for fusion chamber technology journal February 2001
Oscillatory vapour shielding of liquid metal walls in nuclear fusion devices journal August 2017
Low Recycling Divertor for JET Burning Plasma Regime ($P_{\mathrm{DT}}$ > 25 MW, $Q_{\mathrm{DT}}$ > 5), Insensitive to Plasma Physics journal June 2020
First results of the use of a continuously flowing lithium limiter in high performance discharges in the EAST device journal March 2016
Material compatibility with isothermal Pb–Li journal June 2012
A Review of the Present Status and Future Prospects of the Application of Liquid Metals for Plasma-Facing Components in Magnetic Fusion Devices journal October 2015
Results from an improved flowing liquid lithium limiter with increased flow uniformity in high power plasmas in EAST journal November 2018
MHD problems in free liquid surfaces as plasma-facing materials in magnetically confined reactors journal November 2002
Liquid metal “divertorlets” concept for fusion reactors journal December 2020
Exploratory studies of flowing liquid metal divertor options for fusion-relevant magnetic fields in the MTOR facility journal November 2004
Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI journal December 2016
Compatibility of yttria (Y2O3) with liquid lithium journal October 1996
A continuum method for modeling surface tension journal June 1992
Magnetic damping of jets and vortices journal September 1995
Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas journal July 2013
Solutions of uniform, open‐channel, liquid metal flow in a strong, oblique magnetic field journal April 1996
Integrated Liquid Metal Flowing First Wall and Open-Surface Divertor for Fusion Nuclear Science Facility: Concept, Design, and Analysis journal May 2019
Progress on the modeling of liquid metal, free surface, MHD flows for fusion liquid walls journal November 2004
Free surface stability of liquid metal plasma facing components journal August 2016
Development of and experiments with liquid lithium limiters on HT-7 journal July 2013
Lithium–metal infused trenches (LiMIT) for heat removal in fusion devices journal August 2011
Numerical Analysis of Liquid Metal MHD Flow and Heat Transfer for Open-Surface Li Divertor in FNSF journal January 2022
Study of liquid metal surface wave damping in the presence of magnetic fields and electrical currents journal May 2019
Magnetohydrodynamic effects on liquid metal film flowing along an inclined plate relating to plasma facing components journal July 2020
Enhanced Energy Confinement and Performance in a Low-Recycling Tokamak journal August 2006
Evaluating the performance of the two-phase flow solver interFoam journal January 2012
Numerical Simulation of Thin-Film MHD Flow for Nonuniform Conductivity Walls journal February 2021
Initial liquid metal magnetohydrodynamic thin film flow experiments in the McGA-loop facility at UCLA journal March 1995
GaInSn usage in the research laboratory journal May 2008
Exploring liquid metal plasma facing component (PFC) concepts—Liquid metal film flow behavior under fusion relevant magnetic fields journal February 2006
Modeling of liquid lithium flow in porous plasma facing material journal March 2021
Developing solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A: concepts and questions journal April 2022
Design and Analysis of the Liquid Metal Free-Surface Divertor Cooling System journal November 2019
Liquid magnetohydrodynamics — recent progress and future directions for fusion journal November 2000
Design of the Flowing LIquid Torus (FLIT) journal May 2019
MHD Stability Analysis and Flow Controls of Liquid Metal Free Surface Film Flows as Fusion Reactor PFCs journal November 2016
Hydrogen and helium recycling from stirred liquid lithium under steady state plasma bombardment journal December 2014

Figures / Tables (18)