Plasma source development for fusion-relevant material testing

John B.O. Caughman, Richard H. Goulding, Theodore M. Biewer, Timothy S. Bigelow, Ian H. Campbell, Juan Caneses, Stephanie J. Diem, Andy Fadnek, Dan T. Fehling, Ralph C. Isler, Elijah H. Martin, Chad M. Parish, Juergen Rapp, Kun Wang, Clyde J. Beers, David Donovan, Nischal Kafle, Holly B. Ray, Guinevere C. Shaw, Melissa A. Showers

Research output: Contribution to journalArticlepeer-review

41 Scopus citations

Abstract

Plasma-facing materials in the divertor of a magnetic fusion reactor have to tolerate steady state plasma heat fluxes in the range of 10 MW/m2 for ∼107s, in addition to fusion neutron fluences, which can damage the plasma-facing materials to high displacements per atom (dpa) of ∼50 dpa. Materials solutions needed for the plasma-facing components are yet to be developed and tested. The material plasma exposure experiment (MPEX) is a newly proposed steady state linear plasma device designed to deliver the necessary plasma heat flux to a target for testing, including the capability to expose a priori neutron-damaged material samples to those plasmas. The requirements of the plasma source needed to deliver the required heat flux are being developed on the Proto-MPEX device which is a linear high-intensity radio-frequency (RF) plasma source that combines a high-density helicon plasma generator with electron- and ion-heating sections. The device is being used to study the physics of heating overdense plasmas in a linear configuration. The helicon plasma is operated at 13.56 MHz with RF power levels up to 120 kW. Microwaves at 28 GHz (∼30 kW) are coupled to the electrons in the overdense helicon plasma via electron Bernstein waves and ion cyclotron heating at 7-9 MHz (∼30 kW) is via a magnetic beach approach. High plasma densities >6 × 1019/m3 have been produced in deuterium, with electron temperatures that can range from 2 to >10 eV. Operation with on-axis magnetic field strengths between 0.6 and 1.4 T is typical. The plasma heat flux delivered to a target can be >10 MW/m2, depending on the operating conditions. An initial plasma material interaction experiment with a thin tungsten target exposed to this high heat flux in a predominantly helium plasma showed helium bubble formation near the surface, with no indication of source impurity contamination on the target.

Original languageEnglish
Article number03E114
JournalJournal of Vacuum Science and Technology, Part A: Vacuum, Surfaces and Films
Volume35
Issue number3
DOIs
StatePublished - May 1 2017

Funding

The FEI F200X Talos TEM instrument was provided by the U.S. Department of Energy, Office of Nuclear energy, Fuel Cycle R&D program, and the Nuclear Science user facilities. This material is based on work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, under Contract No. DEAC05-00OR22725.

FundersFunder number
Office of Fusion Energy SciencesDEAC05-00OR22725
U.S. Department of Energy
Office of Science
Office of Nuclear Energy
The Ministry of Economic Affairs and Employment

    Fingerprint

    Dive into the research topics of 'Plasma source development for fusion-relevant material testing'. Together they form a unique fingerprint.

    Cite this