Testing of spark plasma sintered porous tungsten under neon glow discharge cleaning conditions in LTX-β

• We demonstrated the in situ cleaning of powder-based PFCs in a fusion reactor. • Porous W samples were fabricated to be used as a CPS with liquid Li. • Analysis confirmed high carbon (C) and oxygen (O) contamination on samples. • Porous W CPS was exposed to Ne Glow Discharge Cleaning (GDC) in LTX-β. • Ne GDC with rapid heating reduces C and O contamination in CPS. This paper demonstrates that tungsten (W) based powder reconstituted Plasma Facing Components (PFCs) can be treated in situ in a fusion reactor to remove W oxide and carbon (C) contamination. Doing so should ease the challenge of using these materials in a Capillary Porous System (CPS) with lithium (Li) by enabling better wetting and less contamination of the Li by the underlying CPS. Most powder reconstituted materials including 3D printed and sintered PFCs suffer from a high surface contamination from oxides and surface C, which complicates their use with liquid Li, a primary PFC candidate. Spark plasma sintered porous W samples were fabricated to be used as a CPS with liquid Li. The samples were characterized in terms of morphology and surface chemistry. Analysis confirms a high C and oxygen (O) contamination. We present the results of exposing this type of CPS to Glow Discharge Cleaning (GDC) cycles in the Lithium Tokamak Experiment-β (LTX-β). The sample was exposed to neon (Ne) GDC in the midplane of the low-field side of LTX-β and analyzed in vacuo with Temperature Programmed Desorption (TPD) and Secondary Ion Mass Spectrometry (SIMS) to investigate the effects the Ne GDC had on the chemical composition of the sample. The combination of Ne GDC with rapid heating as done in TPD was successful in reducing the W oxides and removing the C contamination.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2026-04-13
DOI
https://doi.org/10.1016/j.nme.2026.102123
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.00

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article

Testing of spark plasma sintered porous tungsten under neon glow discharge cleaning conditions in LTX-β

Shota Abe, Alexandru Marin, A. Maan, R. Majeski et al.
Nuclear Materials and Energy
Fusion materials and technologies
article

Testing of spark plasma sintered porous tungsten under neon glow discharge cleaning conditions in LTX-β

Shota Abe, Alexandru Marin, A. Maan, R. Majeski, M. Nieto, Camilo Jaramillo, Ama Dahanayake, B.E. Koel, D. Boyle, T. Le, C. López Pérez
article en

Abstract

• We demonstrated the in situ cleaning of powder-based PFCs in a fusion reactor. • Porous W samples were fabricated to be used as a CPS with liquid Li. • Analysis confirmed high carbon (C) and oxygen (O) contamination on samples. • Porous W CPS was exposed to Ne Glow Discharge Cleaning (GDC) in LTX-β. • Ne GDC with rapid heating reduces C and O contamination in CPS. This paper demonstrates that tungsten (W) based powder reconstituted Plasma Facing Components (PFCs) can be treated in situ in a fusion reactor to remove W oxide and carbon (C) contamination. Doing so should ease the challenge of using these materials in a Capillary Porous System (CPS) with lithium (Li) by enabling better wetting and less contamination of the Li by the underlying CPS. Most powder reconstituted materials including 3D printed and sintered PFCs suffer from a high surface contamination from oxides and surface C, which complicates their use with liquid Li, a primary PFC candidate. Spark plasma sintered porous W samples were fabricated to be used as a CPS with liquid Li. The samples were characterized in terms of morphology and surface chemistry. Analysis confirms a high C and oxygen (O) contamination. We present the results of exposing this type of CPS to Glow Discharge Cleaning (GDC) cycles in the Lithium Tokamak Experiment-β (LTX-β). The sample was exposed to neon (Ne) GDC in the midplane of the low-field side of LTX-β and analyzed in vacuo with Temperature Programmed Desorption (TPD) and Secondary Ion Mass Spectrometry (SIMS) to investigate the effects the Ne GDC had on the chemical composition of the sample. The combination of Ne GDC with rapid heating as done in TPD was successful in reducing the W oxides and removing the C contamination.

Nuclear Materials and EnergyVol. 47
Pennsylvania State University (US), Princeton University (US), Princeton Plasma Physics Laboratory (US), Institute for Nuclear Research Pitesti (RO)
U.S. Department of Energy
Openalex Percentile: Top 29%
Fusion materials and technologies
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