TY - JOUR
T1 - Pre-conceptual design activities for the materials plasma exposure experiment
AU - Lumsdaine, Arnold
AU - Rapp, Juergen
AU - Varma, Venugopal
AU - Bjorholm, Thomas
AU - Bradley, Craig
AU - Caughman, John
AU - Duckworth, Robert
AU - Goulding, Richard
AU - Graves, Van
AU - Giuliano, Dominic
AU - Lessard, Timothy
AU - McGinnis, Dean
AU - Meitner, Steven
N1 - Publisher Copyright:
© 2015 Elsevier B.V.
PY - 2016/11/1
Y1 - 2016/11/1
N2 - The development of next step fusion facilities such as DEMO or a Fusion Nuclear Science Facility (FNSF) requires first closing technology gaps in some 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.
AB - The development of next step fusion facilities such as DEMO or a Fusion Nuclear Science Facility (FNSF) requires first closing technology gaps in some 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.
KW - Linear plasma experiments
KW - Plasma facing components
KW - Plasma-material interactions
KW - R&D facilities
UR - http://www.scopus.com/inward/record.url?scp=84953333797&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2015.10.020
DO - 10.1016/j.fusengdes.2015.10.020
M3 - Article
AN - SCOPUS:84953333797
SN - 0920-3796
VL - 109-111
SP - 1714
EP - 1718
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
ER -