Patrik Tarfila , Oriol Costa Garrido , Boštjan Končar , Francesco Giorgetti , Selanna Roccella
{"title":"Structural analysis of DTT divertor PFU under electromagnetic and thermal loading","authors":"Patrik Tarfila , Oriol Costa Garrido , Boštjan Končar , Francesco Giorgetti , Selanna Roccella","doi":"10.1016/j.fusengdes.2025.114999","DOIUrl":null,"url":null,"abstract":"<div><div>The plasma-facing units (PFU) of the Divertor Tokamak Test facility (DTT) are expected to withstand high heat fluxes as well as electromagnetic (EM) loads during normal and off-normal operations. As the design of the DTT divertor PFU moves forward, specific analyses of the component's real geometry under the expected loads are needed to verify its suitability. This paper presents structural analyses of the DTT divertor PFU under combined loads including EM, thermal and pressure loadings. A single PFU is analyzed under EM loads during the slow plasma Vertical Displacement Event (VDE), together with heat fluxes during single-null (SN) detached plasma configuration. A strategy for using a discrete vector field of EM loads as input data in the ABAQUS environment is described. Due to the rather large displacements obtained with EM loads and the original set of PFU supports, two additional supports are proposed and included in the analyses. The results with the additional supports show an improvement of the stresses and displacements. The analysis with combined loads reveals that the stresses in monoblocks, copper interlayer and weld regions are mainly driven by heat flux and pressure loads, while the EM loads are the source of higher (local) stresses in the CuCrZr pipe and supports.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"215 ","pages":"Article 114999"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-28","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/S0920379625001991","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 plasma-facing units (PFU) of the Divertor Tokamak Test facility (DTT) are expected to withstand high heat fluxes as well as electromagnetic (EM) loads during normal and off-normal operations. As the design of the DTT divertor PFU moves forward, specific analyses of the component's real geometry under the expected loads are needed to verify its suitability. This paper presents structural analyses of the DTT divertor PFU under combined loads including EM, thermal and pressure loadings. A single PFU is analyzed under EM loads during the slow plasma Vertical Displacement Event (VDE), together with heat fluxes during single-null (SN) detached plasma configuration. A strategy for using a discrete vector field of EM loads as input data in the ABAQUS environment is described. Due to the rather large displacements obtained with EM loads and the original set of PFU supports, two additional supports are proposed and included in the analyses. The results with the additional supports show an improvement of the stresses and displacements. The analysis with combined loads reveals that the stresses in monoblocks, copper interlayer and weld regions are mainly driven by heat flux and pressure loads, while the EM loads are the source of higher (local) stresses in the CuCrZr pipe and supports.
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.