Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U

Rindt, P.; Lopes Cardozo, N. J.; van Dommelen, J. A. W.; Kaita, R.; Jaworski, M. A.

doi:10.1016/j.fusengdes.2016.08.020

Title: Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U

Abstract

In this study, a conceptual design for a pre-filled liquid lithium divertor target for the National Spherical Torus Experiment Upgrade (NSTX-U) is presented. The design is aimed at facilitating experiments with high lithium flux from the plasma facing components (PFCs) in NSTX-U and investigating the potential of capillary based liquid lithium components. In the design, lithium is supplied from a reservoir in the PFC to the plasma facing surface via capillary action in a wicking structure. This working principle is also demonstrated experimentally. Next, a titanium zirconium molybdenum (TZM) prototype design is presented, required to withstand a steady state heat flux peaking at 10 MW m^–2 for 5 s and edge localized modes depositing (130 kJ in 2 ms at 10 Hz). The main challenge is to sufficiently reduce the thermal stresses. This is achieved by dividing the surface into brushes and filling the slots in between with liquid lithium. The principle of using this liquid “interlayer” allows for thermal expansion and simultaneously heat conduction, and could be used to significantly reduce the demands to solids in future PFCs. Lithium flow to the surface is analyzed using a novel analytical model, ideally suited for design purposes. Thermal stresses in themore »« less

Authors:

Rindt, P. ^[1]; Lopes Cardozo, N. J. ^[1]; van Dommelen, J. A. W. ^[1];

^[2]; Jaworski, M. A. ^[2]

Eindhoven Univ. of Technology, Eindhoven (The Netherlands)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)

Publication Date:: Sat Sep 03 00:00:00 EDT 2016

Research Org.:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1335696

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 112; Journal Issue: C; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 42 ENGINEERING; fusion; divertor; lithium; capillary; NSTX-U

Citation Formats


                    Rindt, P., Lopes Cardozo, N. J., van Dommelen, J. A. W., Kaita, R., and Jaworski, M. A. Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U.  United States: N. p., 2016. 
Web.  doi:10.1016/j.fusengdes.2016.08.020.

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                    Rindt, P., Lopes Cardozo, N. J., van Dommelen, J. A. W., Kaita, R., & Jaworski, M. A. Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U.  United States.  https://doi.org/10.1016/j.fusengdes.2016.08.020

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                    Rindt, P., Lopes Cardozo, N. J., van Dommelen, J. A. W., Kaita, R., and Jaworski, M. A. Sat .  
"Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U".  United States.  https://doi.org/10.1016/j.fusengdes.2016.08.020.  https://www.osti.gov/servlets/purl/1335696.

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@article{osti_1335696,

  title        = {Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U},

  author       = {Rindt, P. and Lopes Cardozo, N. J. and van Dommelen, J. A. W. and Kaita, R. and Jaworski, M. A.},

  abstractNote = {In this study, a conceptual design for a pre-filled liquid lithium divertor target for the National Spherical Torus Experiment Upgrade (NSTX-U) is presented. The design is aimed at facilitating experiments with high lithium flux from the plasma facing components (PFCs) in NSTX-U and investigating the potential of capillary based liquid lithium components. In the design, lithium is supplied from a reservoir in the PFC to the plasma facing surface via capillary action in a wicking structure. This working principle is also demonstrated experimentally. Next, a titanium zirconium molybdenum (TZM) prototype design is presented, required to withstand a steady state heat flux peaking at 10 MW m–2 for 5 s and edge localized modes depositing (130 kJ in 2 ms at 10 Hz). The main challenge is to sufficiently reduce the thermal stresses. This is achieved by dividing the surface into brushes and filling the slots in between with liquid lithium. The principle of using this liquid “interlayer” allows for thermal expansion and simultaneously heat conduction, and could be used to significantly reduce the demands to solids in future PFCs. Lithium flow to the surface is analyzed using a novel analytical model, ideally suited for design purposes. Thermal stresses in the PFC are analyzed using the finite element method. As a result, the requirements are met, and thus a prototype will be manufactured for physical testing.},

  doi          = {10.1016/j.fusengdes.2016.08.020},

  journal      = {Fusion Engineering and Design},

  number       = C,

  volume       = 112,

  place        = {United States},

  year         = {Sat Sep 03 00:00:00 EDT 2016},

  month        = {Sat Sep 03 00:00:00 EDT 2016}

}

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Wetting properties of liquid lithium on select fusion relevant surfaces
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Recent analysis of key plasma wall interactions issues for ITER
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Roth, Joachim; Tsitrone, E.; Loarte, A.
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Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
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Gray, T. K.; Maingi, R.; Soukhanovskii, V. A.
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Similar Records

Title: Conceptual design of a pre-loaded liquid lithium divertor target for NSTX-U

Abstract

Citation Formats

Recent analysis of key plasma wall interactions issues for ITER journal, June 2009

Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices journal, May 2006

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Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance journal, December 2013

Testing of liquid lithium limiters in CDX-U journal, November 2004

FTU results with a liquid lithium limiter journal, May 2011

Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas journal, July 2013

Calculation and experimental investigation of fusion reactor divertor plate and first wall protection by capillary-pore systems with lithium journal, May 1999

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Overview of the physics and engineering design of NSTX upgrade journal, July 2012

Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX journal, August 2011

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Recrystallization kinetics of warm-rolled tungsten in the temperature range 1150–1350 °C journal, December 2014

La2O3 effects on TZM alloy recovery, recrystallization and mechanical properties journal, June 2015

Permeability of open-pore microcellular materials journal, March 2005

Modeling the reduction of gross lithium erosion observed under high-flux deuterium bombardment journal, August 2015

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Heat Capacity of Reference Materials: Cu and W journal, October 1984

Wetting properties of liquid lithium on select fusion relevant surfaces journal, December 2014

Design Models and Experimental Data for Conceptual Design of a Pre-Loaded Liquid Lithium Divertor Target for NSTX-U dataset, January 2016

Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance journal, December 2013

Wetting properties of liquid lithium on select fusion relevant surfaces journal, December 2014

Recent analysis of key plasma wall interactions issues for ITER journal, June 2009

Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX journal, August 2011

Modeling the reduction of gross lithium erosion observed under high-flux deuterium bombardment journal, August 2015

Development of a liquid-metal fusion reactor divertor with a capillary-pore system journal, October 1996

Heat Capacity of Reference Materials: Cu and W journal, October 1984

High temperature deformation behavior of the molybdenum alloy TZM journal, July 2010

Laboratory Investigation of Vapor Shielding for Lithium-Coated Molybdenum in Devex journal, March 2012

Design Models and Experimental Data for Conceptual Design of a Pre-Loaded Liquid Lithium Divertor Target for NSTX-U dataset, January 2016

Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility journal, June 2019

Power handling limit of liquid lithium divertor targets journal, July 2018

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Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses journal, March 2019

Vapor shielding of liquid lithium divertor target during steady state and transient events journal, January 2020

Recent analysis of key plasma wall interactions issues for ITER
journal, June 2009

Experiments with lithium limiter on T-11M tokamak and applications of the lithium capillary-pore system in future fusion reactor devices
journal, May 2006

Self-Regulated Plasma Heat Flux Mitigation Due to Liquid Sn Vapor Shielding
journal, April 2016

Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance
journal, December 2013

Testing of liquid lithium limiters in CDX-U
journal, November 2004

FTU results with a liquid lithium limiter
journal, May 2011

Liquid lithium divertor characteristics and plasma–material interactions in NSTX high-performance plasmas
journal, July 2013

Calculation and experimental investigation of fusion reactor divertor plate and first wall protection by capillary-pore systems with lithium
journal, May 1999

First results of flowing liquid lithium limiter in HT-7
journal, April 2014

Erosion of lithium coatings on TZM molybdenum and graphite during high-flux plasma bombardment
journal, December 2014

Overview of the physics and engineering design of NSTX upgrade
journal, July 2012

Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
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Capillary wicking of liquid lithium on laser textured surfaces for plasma facing components
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Recrystallization kinetics of warm-rolled tungsten in the temperature range 1150–1350 °C
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La2O3 effects on TZM alloy recovery, recrystallization and mechanical properties
journal, June 2015

Permeability of open-pore microcellular materials
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Modeling the reduction of gross lithium erosion observed under high-flux deuterium bombardment
journal, August 2015

High heat flux capabilities of the Magnum-PSI linear plasma device
journal, October 2013

Improvement in Recrystallization Temperature and Mechanical Properties of a Commercial TZM Alloy through Microstructure Control by Multi-Step Internal Nitriding
journal, January 2005

Dynamic Young’s moduli of tungsten and tantalum at high temperature and stress
journal, February 2011

Thermal Conductivity of the Elements
journal, April 1972

Heat Capacity of Reference Materials: Cu and W
journal, October 1984

Wetting properties of liquid lithium on select fusion relevant surfaces
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Design Models and Experimental Data for Conceptual Design of a Pre-Loaded Liquid Lithium Divertor Target for NSTX-U
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Surface chemistry analysis of lithium conditioned NSTX graphite tiles correlated to plasma performance
journal, December 2013

Wetting properties of liquid lithium on select fusion relevant surfaces
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Recent analysis of key plasma wall interactions issues for ITER
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Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX
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Modeling the reduction of gross lithium erosion observed under high-flux deuterium bombardment
journal, August 2015

Development of a liquid-metal fusion reactor divertor with a capillary-pore system
journal, October 1996

Heat Capacity of Reference Materials: Cu and W
journal, October 1984

High temperature deformation behavior of the molybdenum alloy TZM
journal, July 2010

Laboratory Investigation of Vapor Shielding for Lithium-Coated Molybdenum in Devex
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Design Models and Experimental Data for Conceptual Design of a Pre-Loaded Liquid Lithium Divertor Target for NSTX-U
dataset, January 2016

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Power handling limit of liquid lithium divertor targets
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Power handling and vapor shielding of pre-filled lithium divertor targets in Magnum-PSI
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Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses
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Vapor shielding of liquid lithium divertor target during steady state and transient events
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