Validation of vacuum vessel thermal shield deformation via finite elements and morphing techniques based analysis

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.2025.114937

Edoardo Pompa , Pierric Leonard , Tudorel Popa , Luigi Reccia , Marco E. Biancolini , Gabriele D'Amico , Francisco J. Fuentes

{"title":"Validation of vacuum vessel thermal shield deformation via finite elements and morphing techniques based analysis","authors":"Edoardo Pompa , Pierric Leonard , Tudorel Popa , Luigi Reccia , Marco E. Biancolini , Gabriele D'Amico , Francisco J. Fuentes","doi":"10.1016/j.fusengdes.2025.114937","DOIUrl":null,"url":null,"abstract":"<div><div>The Vacuum Vessel Thermal Shield (VVTS) is the barrier that reduces by two orders of magnitude heat loads transferred by thermal radiation and conduction from hot components to magnets and other systems inside the cryostat that operate at 4 .5K. In order to maintain its function during operation, the clearance between VVTS, Toroidal Field Coils (TFC) and Vacuum Vessel (VV), shall be guaranteed. Hence, it is of paramount importance to monitor the gap during the machine assembly phase, when changes in the constraints of the flexible structure may affect the as-built geometries. In particular, after the assembly of the TF coils on the sector module in the Sectors Sub-Assembly Tools (SSAT), accessibility to the VVTS becomes limited to the area of the sector edge. From this stage on, as-built data of the accessible surfaces may not be representative of the full deformed shape. In order to validate the actual measurement strategy, an analysis based on Finite Elements and Morphing Techniques has been carried out.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114937"},"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/S0920379625001383","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 Vacuum Vessel Thermal Shield (VVTS) is the barrier that reduces by two orders of magnitude heat loads transferred by thermal radiation and conduction from hot components to magnets and other systems inside the cryostat that operate at 4 .5K. In order to maintain its function during operation, the clearance between VVTS, Toroidal Field Coils (TFC) and Vacuum Vessel (VV), shall be guaranteed. Hence, it is of paramount importance to monitor the gap during the machine assembly phase, when changes in the constraints of the flexible structure may affect the as-built geometries. In particular, after the assembly of the TF coils on the sector module in the Sectors Sub-Assembly Tools (SSAT), accessibility to the VVTS becomes limited to the area of the sector edge. From this stage on, as-built data of the accessible surfaces may not be representative of the full deformed shape. In order to validate the actual measurement strategy, an analysis based on Finite Elements and Morphing Techniques has been carried out.

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.