Initial design concepts for solid boron injection in ITER

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY
J.A. Snipes , L.R. Baylor , A. Bortolon , F. Effenberg , E.P. Gilson , A. Loarte , R. Lunsford , R. Maingi , S. Meitner , F. Nespoli , S. Maruyama , A. Nagy , Z. Sun , J. Ulreich , T. Wauters
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引用次数: 0

Abstract

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.
在国际热核实验堆中注入固体硼的初步设计概念
作为热核实验堆将其第一壁材料从铍改为钨的考虑的一部分,热核实验堆组织建议研究向等离子体中实时注入固体硼(SBI)的可行性,以便对壁和分流器进行涂层,补充辉光放电硼化(GDB)[1]。硼可沉积获取氧,减少等离子体面组件(PFC)中钨的溅射。特别是在等离子体壁相互作用明显的区域,硼涂层在高性能等离子体条件下的寿命预计会很短。拟议的 SBI 系统旨在维持这些区域的硼层,以避免等离子体中钨的过度辐射,从而降低风险,确保热核实验堆能够达到并维持 Q = 10 的条件。该系统将尽量少用,因为硼的再沉积会导致大量氚的滞留,而在热核实验堆中必须尽量减少氚的滞留,以符合核安全要求。建议使用 SBI 来限制和精确控制等离子体运行期间实时注入的硼量。在此,根据以前在世界各地的一些托卡马克和恒星器上使用 SBI 系统取得的成果,介绍了热核实验堆中 SBI 系统的一些设计要求和初步概念[2]、[3]、[4]、[5]、[6]、[7]、[8]、[9]、[10]、[11]、[12]、[13]、[14]、[15]、[16]、[17]、[18]。PPPL 安装的 SBI 系统在 AUG[4]、DIII-D[5]、EAST[6]、KSTAR[7]、LHD[8]、TFTR[9]、WEST[10]和 W7-X [11]、[12]的等离子体运行期间,以 2-200 mg/s 的校准速率实时注入了直径为 5 µm-2 mm 的硼粒子,从而改善了壁面条件,降低了等离子体杂质浓度和辐射功率,并提高了等离子体性能。硼在等离子体边缘电离,然后沉积在等离子体润湿的表面上。在 AUG[4]、EAST[6]和 WEST[10]上,使用 SBI 进行几次放电后,观察到钨溅射源减少了。对这些 SBI 结果进行了推断,以估算热核实验堆中壁面调节所需的硼量。还介绍了热核实验堆的实时 SBI 控制要求和等离子体运行方案。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
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