Development of tungsten fiber-reinforced copper composite pipes for EU-DEMO Divertor target

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

Fusion Engineering and Design Pub Date : 2025-03-20 DOI:10.1016/j.fusengdes.2025.114973

P. Lorusso , S. Roccella , E. Cacciotti , M. Cerocchi , F. Crea , R. De Luca , L. Verdini , P. Junghanns , K. Hunger , A. von Müller , J.H. You

{"title":"Development of tungsten fiber-reinforced copper composite pipes for EU-DEMO Divertor target","authors":"P. Lorusso , S. Roccella , E. Cacciotti , M. Cerocchi , F. Crea , R. De Luca , L. Verdini , P. Junghanns , K. Hunger , A. von Müller , J.H. You","doi":"10.1016/j.fusengdes.2025.114973","DOIUrl":null,"url":null,"abstract":"<div><div>Within the roadmap of the EU-DEMO reactor design pursued by the EUROfusion Programme, R&D activities are promoted for the technological development of Plasma Facing Components. A dedicated task aims at consolidating and verifying the current target concepts envisioned for DEMO Divertor, derived from the reference ITER-like W-monoblock concept and the back-up solution with tungsten fiber-reinforced copper (W<sub>f</sub>-Cu) composite pipes. ENEA has undertaken a research activity to support the back-up concept, finding alternative technological solutions for monoblock-pipe joining to reduce the use of materials having high activation and/or degradation under neutron irradiation. In particular, the possibility of joining the blocks to the pipe without brazing alloy has been investigated. An impregnation procedure consisting of copper casting with the simultaneous impregnation of pre-wrapped W fibers and the junction of the W monoblocks in a single process has been developed. A crucial point is the realization of high-quality composite tubes, having dimensions as close as possible to the ones of the standard CuCrZr tubes currently envisaged for DEMO Divertor, as well as a Cu matrix in which the content of defects and imperfections is reduced as much as possible. For this purpose, a set of samples having a DEMO Divertor target cooling tube shape are fabricated, and their quality is assessed through non-destructive (ultrasonic testing) and destructive (i.e., metallography) examination techniques.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114973"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-20","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/S0920379625001735","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

Within the roadmap of the EU-DEMO reactor design pursued by the EUROfusion Programme, R&D activities are promoted for the technological development of Plasma Facing Components. A dedicated task aims at consolidating and verifying the current target concepts envisioned for DEMO Divertor, derived from the reference ITER-like W-monoblock concept and the back-up solution with tungsten fiber-reinforced copper (W_f-Cu) composite pipes. ENEA has undertaken a research activity to support the back-up concept, finding alternative technological solutions for monoblock-pipe joining to reduce the use of materials having high activation and/or degradation under neutron irradiation. In particular, the possibility of joining the blocks to the pipe without brazing alloy has been investigated. An impregnation procedure consisting of copper casting with the simultaneous impregnation of pre-wrapped W fibers and the junction of the W monoblocks in a single process has been developed. A crucial point is the realization of high-quality composite tubes, having dimensions as close as possible to the ones of the standard CuCrZr tubes currently envisaged for DEMO Divertor, as well as a Cu matrix in which the content of defects and imperfections is reduced as much as possible. For this purpose, a set of samples having a DEMO Divertor target cooling tube shape are fabricated, and their quality is assessed through non-destructive (ultrasonic testing) and destructive (i.e., metallography) examination techniques.

查看原文本刊更多论文

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.