Effect of ion irradiation on the surface electrical conductivity of CuCrZr at high frequencies

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-05-27 DOI:10.1016/j.fusengdes.2025.115197

C. Marraco Borderas , J. Genoud , R. Chavan , T.P. Goodman , P. Petersson , A. Xydou , A. Mas Sánchez , D. Birlan , J-P. Hogge

{"title":"Effect of ion irradiation on the surface electrical conductivity of CuCrZr at high frequencies","authors":"C. Marraco Borderas , J. Genoud , R. Chavan , T.P. Goodman , P. Petersson , A. Xydou , A. Mas Sánchez , D. Birlan , J-P. Hogge","doi":"10.1016/j.fusengdes.2025.115197","DOIUrl":null,"url":null,"abstract":"<div><div>The ohmic losses in the Electron Cyclotron Heating system of the DEMO nuclear fusion reactor depend on the surface electrical conductivity of the material at the frequency of the mm-wave beams generated in the gyrotrons. To reduce the ohmic losses, many components will be made or coated with materials with high electrical conductivity, such as CuCrZr. In addition, in the Equatorial Port Plug these components will also have to withstand very high irradiation doses. The objective of this work was to study the effect of ion irradiation on the surface electrical conductivity of CuCrZr at frequencies between 140 and 170 GHz. The samples were irradiated with Cu ions at 1, 3 and 10 dpa, which did not entail any change in the surface roughness, and were measured using a Fabry-Pérot resonator. In addition, SEM-EDX analysis was performed to chemically characterize the surface of the samples. The results show that the surface electrical conductivity is reduced by more than 40 % at 10 dpa, which would translate in a significant increase of the ohmic losses, rising the cooling needs of the components in the Electron Cyclotron Heating system.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"218 ","pages":"Article 115197"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S092037962500393X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

The ohmic losses in the Electron Cyclotron Heating system of the DEMO nuclear fusion reactor depend on the surface electrical conductivity of the material at the frequency of the mm-wave beams generated in the gyrotrons. To reduce the ohmic losses, many components will be made or coated with materials with high electrical conductivity, such as CuCrZr. In addition, in the Equatorial Port Plug these components will also have to withstand very high irradiation doses. The objective of this work was to study the effect of ion irradiation on the surface electrical conductivity of CuCrZr at frequencies between 140 and 170 GHz. The samples were irradiated with Cu ions at 1, 3 and 10 dpa, which did not entail any change in the surface roughness, and were measured using a Fabry-Pérot resonator. In addition, SEM-EDX analysis was performed to chemically characterize the surface of the samples. The results show that the surface electrical conductivity is reduced by more than 40 % at 10 dpa, which would translate in a significant increase of the ohmic losses, rising the cooling needs of the components in the Electron Cyclotron Heating system.

查看原文本刊更多论文

离子辐照对CuCrZr高频表面电导率的影响

DEMO核聚变反应堆电子回旋加速器加热系统的欧姆损耗取决于材料在回旋加速器产生的毫米波波束频率下的表面导电性。为了减少欧姆损耗，许多元件将被制成或涂覆具有高导电性的材料，如CuCrZr。此外，在赤道港塞，这些组件还必须承受非常高的辐照剂量。本研究的目的是研究离子辐照对CuCrZr在140 ~ 170 GHz频率下表面电导率的影响。样品以1、3和10 dpa的铜离子照射，表面粗糙度没有任何变化，并使用fabry - p谐振器进行测量。此外，SEM-EDX分析进行了化学表征样品的表面。结果表明，在10 dpa时，表面电导率降低了40%以上，这将导致欧姆损失的显著增加，从而增加了电子回旋加热系统中组件的冷却需求。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.