SiC as a core-edge integrated wall solution in DIII-D

S. Zamperini; T. Abrams; J. Nichols; E. Unterberg; A. Lasa; P. Stangeby; S. Bringuier; D. Rudakov; J. D. Elder

doi:10.1016/j.nme.2023.101535

SiC as a core-edge integrated wall solution in DIII-D

S. Zamperini, T. Abrams, J. Nichols, E. Unterberg, A. Lasa, P. Stangeby, S. Bringuier, D. Rudakov, J. D. Elder

Power Exhaust and Particle Control

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1 Scopus citations

Abstract

Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Z_eff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Z_eff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Z_eff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented.

Original language	English
Article number	101535
Journal	Nuclear Materials and Energy
Volume	37
DOIs	https://doi.org/10.1016/j.nme.2023.101535
State	Published - Dec 2023

Funding

This material is based upon work supported by the U.S. Department of Energy, Office of Science, Office of Fusion Energy Sciences, using the DIII-D National Fusion Facility, a DOE Office of Science user facility, under Awards DE-FC02-04ER54698, DE-FG02-07ER54917 and DE-AC05-00OR22725. Disclaimer: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

Funders	Funder number
DOE Office of Science user facility	DE-AC05-00OR22725, DE-FC02-04ER54698, DE-FG02-07ER54917
United States Government
U.S. Department of Energy
Office of Science
Fusion Energy Sciences

Keywords

DIII-D
DIVIMP
impurity transport
nuclear fusion
silicon carbide
wall conditioning

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.nme.2023.101535

Cite this

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title = "SiC as a core-edge integrated wall solution in DIII-D",

abstract = "Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Zeff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Zeff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Zeff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented.",

keywords = "DIII-D, DIVIMP, impurity transport, nuclear fusion, silicon carbide, wall conditioning",

author = "S. Zamperini and T. Abrams and J. Nichols and E. Unterberg and A. Lasa and P. Stangeby and S. Bringuier and D. Rudakov and Elder, {J. D.}",

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T1 - SiC as a core-edge integrated wall solution in DIII-D

AU - Zamperini, S.

AU - Abrams, T.

AU - Nichols, J.

AU - Unterberg, E.

AU - Lasa, A.

AU - Stangeby, P.

AU - Bringuier, S.

AU - Rudakov, D.

AU - Elder, J. D.

PY - 2023/12

Y1 - 2023/12

N2 - Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Zeff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Zeff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Zeff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented.

AB - Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation [1,2]. To assess SiC as a main wall material in DIII-D, simulations with TRIM.SP and DIVIMP are performed on a well-diagnosed L-mode discharge. The effective charge, Zeff, across the separatrix is used as a figure of merit in comparing SiC to the current graphite walls. It is found that SiC is expected to reduce Zeff, potentially by as much as ∼50 %. It is discussed how SiC may be expected to “self-condition” and create wall conditions similar to siliconization, further lowering Zeff due to efficient oxygen gettering. The potential benefits are reviewed and a path towards SiC walls in DIII-D is presented.

KW - DIII-D

KW - DIVIMP

KW - impurity transport

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KW - silicon carbide

KW - wall conditioning

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JO - Nuclear Materials and Energy

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ER -

SiC as a core-edge integrated wall solution in DIII-D

Abstract

Funding

Keywords

UN SDGs

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