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Title: Pre-conceptual design activities for the materials plasma exposure experiment

Abstract

The development of next step fusion facilities such as DEMO or a Fusion Nuclear Science Facility (FNSF) requires first closing technology gaps in a few critical areas. Understanding the material-plasma interface is necessary to enable the development of divertors for long-pulse plasma facilities. A pre-conceptual design for a proposed steady-state linear plasma device, the Materials Plasma Exposure Experiment (MPEX), is underway. A helicon plasma source along with ion cyclotron and electron Bernstein wave heating systems will produce ITER divertor relevant plasma conditions with steady-state parallel heat fluxes of up to 40 MW/m2 with ion fluxes up to 1024/m2 s on target. Current plans are for the device to use superconducting magnets to produce 1–2 T fields. As a steady-state device, active cooling will be required for components that interact with the plasma (targets, limiters, etc.), as well as for other plasma facing components (transport regions, vacuum tanks, diagnostic ports). Design concepts for the vacuum system, the cooling system, and the plasma heating systems have been completed. The device will include the capability for handling samples that have been neutron irradiated in order to consider the multivariate effects of neutrons, plasma, and high heat-flux on the microstructure of divertor candidate materials.more » A vacuum cask, which can be disconnected from the high field environment in order to perform in-vacuo diagnosis of the surface evolution is also planned for the facility.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
OSTI Identifier:
1394524
Alternate Identifier(s):
OSTI ID: 1397337
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Accepted Manuscript
Journal Name:
Fusion Engineering and Design
Additional Journal Information:
Journal Volume: 109-111; Journal Issue: PB; Journal ID: ISSN 0920-3796
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; plasma facing components; plasma-material interactions; R&D facilities; linear plasma experiments

Citation Formats

Lumsdaine, Arnold, Rapp, Juergen, Varma, Venugopal, Bjorholm, Thomas, Bradley, Craig, Caughman, John, Duckworth, Robert, Goulding, Richard, Graves, Van, Giuliano, Dominic, Lessard, Timothy, McGinnis, Dean, and Meitner, Steven. Pre-conceptual design activities for the materials plasma exposure experiment. United States: N. p., 2016. Web. doi:10.1016/j.fusengdes.2015.10.020.
Lumsdaine, Arnold, Rapp, Juergen, Varma, Venugopal, Bjorholm, Thomas, Bradley, Craig, Caughman, John, Duckworth, Robert, Goulding, Richard, Graves, Van, Giuliano, Dominic, Lessard, Timothy, McGinnis, Dean, & Meitner, Steven. Pre-conceptual design activities for the materials plasma exposure experiment. United States. https://doi.org/10.1016/j.fusengdes.2015.10.020
Lumsdaine, Arnold, Rapp, Juergen, Varma, Venugopal, Bjorholm, Thomas, Bradley, Craig, Caughman, John, Duckworth, Robert, Goulding, Richard, Graves, Van, Giuliano, Dominic, Lessard, Timothy, McGinnis, Dean, and Meitner, Steven. Thu . "Pre-conceptual design activities for the materials plasma exposure experiment". United States. https://doi.org/10.1016/j.fusengdes.2015.10.020. https://www.osti.gov/servlets/purl/1394524.
@article{osti_1394524,
title = {Pre-conceptual design activities for the materials plasma exposure experiment},
author = {Lumsdaine, Arnold and Rapp, Juergen and Varma, Venugopal and Bjorholm, Thomas and Bradley, Craig and Caughman, John and Duckworth, Robert and Goulding, Richard and Graves, Van and Giuliano, Dominic and Lessard, Timothy and McGinnis, Dean and Meitner, Steven},
abstractNote = {The development of next step fusion facilities such as DEMO or a Fusion Nuclear Science Facility (FNSF) requires first closing technology gaps in a few critical areas. Understanding the material-plasma interface is necessary to enable the development of divertors for long-pulse plasma facilities. A pre-conceptual design for a proposed steady-state linear plasma device, the Materials Plasma Exposure Experiment (MPEX), is underway. A helicon plasma source along with ion cyclotron and electron Bernstein wave heating systems will produce ITER divertor relevant plasma conditions with steady-state parallel heat fluxes of up to 40 MW/m2 with ion fluxes up to 1024/m2 s on target. Current plans are for the device to use superconducting magnets to produce 1–2 T fields. As a steady-state device, active cooling will be required for components that interact with the plasma (targets, limiters, etc.), as well as for other plasma facing components (transport regions, vacuum tanks, diagnostic ports). Design concepts for the vacuum system, the cooling system, and the plasma heating systems have been completed. The device will include the capability for handling samples that have been neutron irradiated in order to consider the multivariate effects of neutrons, plasma, and high heat-flux on the microstructure of divertor candidate materials. A vacuum cask, which can be disconnected from the high field environment in order to perform in-vacuo diagnosis of the surface evolution is also planned for the facility.},
doi = {10.1016/j.fusengdes.2015.10.020},
journal = {Fusion Engineering and Design},
number = PB,
volume = 109-111,
place = {United States},
year = {Thu Jan 07 00:00:00 EST 2016},
month = {Thu Jan 07 00:00:00 EST 2016}
}

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Works referenced in this record:

Optimization and limitations of known DEMO divertor concepts
journal, August 2012


High heat flux components—Readiness to proceed from near term fusion systems to power plants
journal, January 2010


DEMO and fusion power plant conceptual studies in Europe
journal, February 2006


Construction of the plasma-wall experiment Magnum-PSI
journal, December 2010


The Development of Plasma-Material Interaction Facilities for the Future of Fusion Technology
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  • Rapp, J.; Biewer, T. M.; Canik, J.
  • Fusion Science and Technology, Vol. 64, Issue 2
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Transport simulations of linear plasma generators with the B2.5-Eirene and EMC3-Eirene codes
journal, August 2015