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Conceptual Design and Analysis of In-Vessel Components for the Materials Plasma Exposure eXperiment (MPEX)

Conference ·
The materials plasma exposure experiment (MPEX) is a linear plasma divertor simulator currently undergoing conceptual design. The facility will expose material samples to steady-state plasma fluxes to examine plasma–material interactions (PMIs) that are expected in the next generation of fusion devices. The plasmas will be generated by a helicon source, with electron and ion heating sources of up to 800 kW possible. The peak heat fluxes of the target are expected to be up to 10 MW/m 2 . The facility will be capable of handling low-activation neutron-irradiated samples in order to examine the multivariate effects of neutron damage and plasma fluence. Neutron-irradiated samples are planned to be roughly of 10-mm diameter; however, plasma-facing components up to 60×600 mm can be accommodated. The steady-state nature of the device will require the magnetic confinement of the plasma to be achieved with superconducting magnets, with a maximum on-axis field of 2.5 T. In addition, since MPEX will be a steady-state device, in-vessel components need to be water cooled. The primary in-vessel components will be the target, the dump plate, the limiter, the skimmers, and the microwave absorber. The conceptual design of these components is presented here, including analyses that confirm that the designs are adequate to meet the requirements of MPEX operation.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE; USDOE Office of Science (SC)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1649566
Country of Publication:
United States
Language:
English

References (15)

Tritium Plasma Experiment Upgrade and Improvement of Surface Diagnostic Capabilities at STAR Facility for Enhancing Tritium and Nuclear PMI Sciences journal April 2017
Progress in magnet design activities for the material plasma exposure experiment journal November 2017
The Challenges of Plasma Material Interactions in Nuclear Fusion Devices and Potential Solutions journal June 2017
Vacuum System and Modeling for the Materials Plasma Exposure Experiment journal August 2017
Heat flux estimates of power balance on Proto-MPEX with IR imaging journal August 2016
Power accounting of plasma discharges in the linear device Proto-MPEX journal April 2018
The Development of Plasma-Material Interaction Facilities for the Future of Fusion Technology journal August 2013
Developing the science and technology for the Material Plasma Exposure eXperiment journal July 2017
Differential pumping requirements for the light-ion helicon source and heating systems of Proto-MPEX journal August 2018
Design and Analysis of an Actively Cooled Window for a High-Power Helicon Plasma Source journal January 2019
Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency journal January 2019
Neutron-Irradiated Samples as Test Materials for MPEX journal November 2015
The Development of the Material Plasma Exposure Experiment journal December 2016
Latest Results from Proto-MPEX and the Future Plans for MPEX journal June 2019
High-Heat-Flux Target Design for the Material Plasma Exposure eXperiment journal July 2019

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