Initial design concepts for solid boron injection in ITER

• Novel approaches to solid boron injection in a harsh nuclear environment. • Proposal of boron gravitational injection or pneumatic gas injection. • Estimates to quantify real-time boron wall conditioning in a large fusion device. As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to supplement glow discharge boronization (GDB) [1] . Boron deposits getter oxygen and reduce sputtering of tungsten from plasma facing components (PFCs). Particularly in areas with significant plasma wall interactions, boron coatings are expected to be short-lived under high performance plasma conditions. The proposed SBI system aims to maintain boron layers in these areas to avoid excessive radiation from tungsten in the plasma as a risk mitigation to ensure ITER will be able to reach and sustain Q = 10 conditions. The system will be used sparingly, as redeposition of boron can lead to significant tritium retention, which must be minimized in ITER to comply with nuclear safety concerns. SBI is proposed to limit and precisely control the amount of boron injected in real-time during plasma operation. Here, some of the design requirements and initial concepts for an SBI system in ITER are presented based on previous results carried out with SBI systems on a number of tokamaks and stellarators around the world [2] , [3] , [4] , [5] , [6] , [7] , [8] , [9] , [10] , [11] , [12] , [13] , [14] , [15] , [16] , [17] , [18] . Previous results using SBI systems installed by PPPL have injected boron particles from 5 µm–2 mm diameter at calibrated rates of 2–200 mg/s in real-time during plasma operation on AUG [4] , DIII-D [5] , EAST [6] , KSTAR [7] , LHD [8] , TFTR [9] , WEST [10] , and W7-X [11] , [12] , leading to improved wall conditions with reduced plasma impurity concentrations and radiated power and improved plasma performance. The boron is ionized in the plasma edge and then deposited on plasma-wetted surfaces. On AUG [4] , EAST [6] and WEST [10] reduced tungsten sputtering sources were observed following several discharges with SBI. Extrapolation of these SBI results are presented to estimate the amount of boron needed for wall conditioning in ITER. Real-time SBI control requirements and plasma operation scenarios for ITER are also described.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-11-08
DOI
https://doi.org/10.1016/j.nme.2024.101809
Citations
12
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
1.41

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article

Initial design concepts for solid boron injection in ITER

T. Wauters, R. Lunsford, A. Nagy, J. Ulreich et al.
12 citations
Nuclear Materials and Energy
Fusion materials and technologies
1.41
article

Initial design concepts for solid boron injection in ITER

T. Wauters, R. Lunsford, A. Nagy, J. Ulreich, F. Nespoli, Shingo Maruyama, R. Maingi, E.P. Gilson, F. Effenberg, L. R. Baylor, S. J. Meitner, J. Snipes, A. Bortolon, A. Loarte, Zhen Sun
article en
12 citations

Abstract

• Novel approaches to solid boron injection in a harsh nuclear environment. • Proposal of boron gravitational injection or pneumatic gas injection. • Estimates to quantify real-time boron wall conditioning in a large fusion device. As part of ITER’s consideration to change its first wall material from beryllium to tungsten, the ITER Organization has proposed studying the feasibility of real-time solid boron injection (SBI) into the plasma to coat the walls and divertor to supplement glow discharge boronization (GDB) [1] . Boron deposits getter oxygen and reduce sputtering of tungsten from plasma facing components (PFCs). Particularly in areas with significant plasma wall interactions, boron coatings are expected to be short-lived under high performance plasma conditions. The proposed SBI system aims to maintain boron layers in these areas to avoid excessive radiation from tungsten in the plasma as a risk mitigation to ensure ITER will be able to reach and sustain Q = 10 conditions. The system will be used sparingly, as redeposition of boron can lead to significant tritium retention, which must be minimized in ITER to comply with nuclear safety concerns. SBI is proposed to limit and precisely control the amount of boron injected in real-time during plasma operation. Here, some of the design requirements and initial concepts for an SBI system in ITER are presented based on previous results carried out with SBI systems on a number of tokamaks and stellarators around the world [2] , [3] , [4] , [5] , [6] , [7] , [8] , [9] , [10] , [11] , [12] , [13] , [14] , [15] , [16] , [17] , [18] . Previous results using SBI systems installed by PPPL have injected boron particles from 5 µm–2 mm diameter at calibrated rates of 2–200 mg/s in real-time during plasma operation on AUG [4] , DIII-D [5] , EAST [6] , KSTAR [7] , LHD [8] , TFTR [9] , WEST [10] , and W7-X [11] , [12] , leading to improved wall conditions with reduced plasma impurity concentrations and radiated power and improved plasma performance. The boron is ionized in the plasma edge and then deposited on plasma-wetted surfaces. On AUG [4] , EAST [6] and WEST [10] reduced tungsten sputtering sources were observed following several discharges with SBI. Extrapolation of these SBI results are presented to estimate the amount of boron needed for wall conditioning in ITER. Real-time SBI control requirements and plasma operation scenarios for ITER are also described.

Nuclear Materials and EnergyVol. 41
ITER (FR), Oak Ridge National Laboratory (US), Princeton Plasma Physics Laboratory (US)
U.S. Department of Energy, Office of Science, Fusion Energy Sciences, Oak Ridge National Laboratory, Princeton Plasma Physics Laboratory
Openalex Percentile: Top 15%
Fusion materials and technologies
1.41
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