Thermal Stability and Corrosion Resistance in Liquid Lithium of Brazed Tungsten Smart Alloy/RAFM Steel Joints

IF 1.9 4区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Journal of Fusion Energy Pub Date : 2024-12-10 DOI:10.1007/s10894-024-00472-1

V. O. Kirillova, N. S. Popov, O. N. Sevryukov, X. Tan, A. A. Bazhenov, S. M. Irmagambetova, A. N. Suchkov

{"title":"Thermal Stability and Corrosion Resistance in Liquid Lithium of Brazed Tungsten Smart Alloy/RAFM Steel Joints","authors":"V. O. Kirillova, N. S. Popov, O. N. Sevryukov, X. Tan, A. A. Bazhenov, S. M. Irmagambetova, A. N. Suchkov","doi":"10.1007/s10894-024-00472-1","DOIUrl":null,"url":null,"abstract":"<div><p>Oxidation resistant smart tungsten alloys (SA) are considered a promising plasma facing material for DEMO reactors. SA-based plasma facing components (PFC) have to meet several long-term operation requirements. Among other criteria, these PFC should be able to withstand high thermal loads and be corrosion resistant in liquid lithium for a liquid first wall design implementation. In this work, smart tungsten alloys WCrY, WCrZr were brazed to reduced activation ferritic-martensitic (RAFM) steels Eurofer97, CLAM via 48Ti–48Zr–4Be wt.% brazing alloy. Thermal stability of the brazed joints was investigated. High temperature shear tests at 300, 600 °C were carried out. The shear strength of WCrZr/Ta/CLAM joints is 50 ± 4 and 49 ± 5 MPa at 300 and 600 °C, respectively. Unbrazing of the WCrY/Ta/Eurofer97 and WCrZr/Ta/CLAM joints occurs at 1447 and 1522 °C, respectively, due to the melting of steels. Corrosion resistance of the smart tungsten alloys, SA/Ta/RAFM joints in liquid lithium at 600 °C, 100 h exposure was demonstrated.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"44 1","pages":""},"PeriodicalIF":1.9000,"publicationDate":"2024-12-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-024-00472-1","RegionNum":4,"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

Oxidation resistant smart tungsten alloys (SA) are considered a promising plasma facing material for DEMO reactors. SA-based plasma facing components (PFC) have to meet several long-term operation requirements. Among other criteria, these PFC should be able to withstand high thermal loads and be corrosion resistant in liquid lithium for a liquid first wall design implementation. In this work, smart tungsten alloys WCrY, WCrZr were brazed to reduced activation ferritic-martensitic (RAFM) steels Eurofer97, CLAM via 48Ti–48Zr–4Be wt.% brazing alloy. Thermal stability of the brazed joints was investigated. High temperature shear tests at 300, 600 °C were carried out. The shear strength of WCrZr/Ta/CLAM joints is 50 ± 4 and 49 ± 5 MPa at 300 and 600 °C, respectively. Unbrazing of the WCrY/Ta/Eurofer97 and WCrZr/Ta/CLAM joints occurs at 1447 and 1522 °C, respectively, due to the melting of steels. Corrosion resistance of the smart tungsten alloys, SA/Ta/RAFM joints in liquid lithium at 600 °C, 100 h exposure was demonstrated.

Abstract Image

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

钨智能合金/RAFM钢钎焊接头的热稳定性和耐锂液腐蚀性能

抗氧化智能钨合金（SA）被认为是一种很有前途的等离子体表面材料。基于sa的等离子体表面元件（PFC）必须满足几个长期的操作要求。在其他标准中，这些PFC应该能够承受高热负荷，并且在液体锂中耐腐蚀，以实现液体第一壁设计。本研究采用48Ti-48Zr-4Be wt.%钎焊合金，将WCrY、WCrZr智能钨合金与低活化铁素体-马氏体（RAFM）钢Eurofer97、CLAM进行钎焊。研究了钎焊接头的热稳定性。在300、600℃下进行了高温剪切试验。300℃和600℃时，WCrZr/Ta/CLAM接头的抗剪强度分别为50±4 MPa和49±5 MPa。WCrY/Ta/Eurofer97和WCrZr/Ta/CLAM接头在1447°C和1522°C时，由于钢的熔化而发生非钎焊。研究了智能钨合金SA/Ta/RAFM接头在液态锂中600℃、100 h的耐蚀性。

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分钟内获得全文去求助

来源期刊

Journal of Fusion Energy 工程技术-核科学技术

CiteScore

2.20

自引率

0.00%

发文量

审稿时长

2.3 months

期刊介绍： The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.