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Latest Results from Proto-MPEX and the Future Plans for MPEX

Journal Article · · Fusion Science and Technology
 [1];  [1];  [2];  [1];  [1];  [1];  [1];  [1];  [2];  [1];  [2];  [3];  [2];  [2]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); University of Tennessee, Knoxville, TN (United States)
  3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); University of Illinois, Urbana-Champaign, IL (United States)
The Prototype Material Plasma Exposure eXperiment (Proto-MPEX) is being used to qualify the plasma source and heating systems for the Material Plasma Exposure eXperiment (MPEX). The MPEX will address important and urgent research needs on plasma material interactions for future fusion reactors. In MPEX, plasma-facing components (nonirradiated and a priori neutron irradiated) will be exposed to plasma conditions as they are expected in future fusion reactors. The MPEX, a steady-state device enabled by superconducting magnets, will be able to break into new ground by assessing plasma-facing materials and components at an ion fluence level in the range of 1030 to 1031 m-2. To achieve the relevant plasma conditions, high-density plasmas (>4 × 1019 m-3) are produced with a high-power helicon source. The so-produced low-temperature helicon plasma is then additionally heated with waves in the ion cyclotron resonance frequency and electron cyclotron resonance frequency domains. Proto-MPEX has achieved all key parameters (source ne, source Te, source Ti, target Te, target Ti, target ion flux, and target heat flux) within a factor of 2 of the design requirements of MPEX, albeit not simultaneously. These parameters were achieved with a total installed heating power of 330 kW, which is less than half of the planned heating power in the MPEX (800 kW). An overview of the latest results from Proto-MPEX is given. These results are shown in relationship to the MPEX system goals. Remaining necessary research and development tasks are discussed. The MPEX is currently in the conceptual design phase. Lastly, the status of the design and an overview of the system requirements are presented.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1649621
Journal Information:
Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 7 Vol. 75; ISSN 1536-1055
Publisher:
American Nuclear SocietyCopyright Statement
Country of Publication:
United States
Language:
English

References (17)

Pre-conceptual design activities for the materials plasma exposure experiment journal November 2016
Progress in magnet design activities for the material plasma exposure experiment journal November 2017
Operational domain of Proto-MPEX journal November 2018
Transport simulations of linear plasma generators with the B2.5-Eirene and EMC3-Eirene codes journal August 2015
First results from the Thomson scattering diagnostic on proto-MPEX journal August 2016
Helicon plasma ion temperature measurements and observed ion cyclotron heating in proto-MPEX journal January 2018
Observations of electron heating during 28 GHz microwave power application in proto-MPEX journal February 2018
An electron Bernstein wave heating scheme for the Proto-MPEX linear device journal July 2018
Dual-pass upgrade to the Thomson scattering diagnostic on the Prototype-Material Plasma Exposure eXperiment (Proto-MPEX) journal October 2018
Vacuum System and Modeling for the Materials Plasma Exposure Experiment journal August 2017
Progress in the Development of a High Power Helicon Plasma Source for the Materials Plasma Exposure Experiment journal August 2017
RF compensation of double Langmuir probes: modelling and experiment journal May 2015
Developing the science and technology for the Material Plasma Exposure eXperiment journal July 2017
The Development of the Material Plasma Exposure Experiment journal December 2016
Plasma source development for fusion-relevant material testing
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  • Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, Vol. 35, Issue 3 https://doi.org/10.1116/1.4982664
journal May 2017
ELMO Bumpy Torus: An alternate concept to tokamaks and mirrors journal April 1981
Neutron-Irradiated Samples as Test Materials for MPEX journal November 2015

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