Status of design and manufacturing qualification activities of the first wall of the Divertor Tokamak test facility

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-16 DOI:10.1016/j.fusengdes.2025.115435

M. Furno Palumbo , S. Roccella , G. De Sano , R. De Luca , M. Iafrati , A. Tatì , B. Riccardi , D. Paoletti , G.M. Polli

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引用次数: 0

Abstract

This paper gives an overview of the current design of the First Wall (FW) of the Divertor Tokamak Test facility (DTT) under construction at Enea Research Centre of Frascati (Rome), as well as the qualification activities related to the manufacturing process of the FW small scale mock-ups.

The main goal of the overview is to illustrate the latest release of the FW component’s design, in accordance with many constraints stemming from the Physics and DTT system interface, at both Inboard (IFW) and Outboard (OFW) side of the DTT device.

Concerning the qualification activities related to the manufacturing of FW preliminary small-scale mock-ups, different technologies were compared. Regarding the OFW plasma facing units (PFUs), the machining and welding processes – TIG, Laser and Electron Beam (EB) – are investigated as conventional manufacturing solutions. The additive manufacturing technology of selective laser melting is considered a valuable procedure that makes a as the best compromise between the manufacturability, performance and costs. Regarding the IFW, the small-scale mock-ups to be manufactured and qualified concern the limiter module. It will be adopted, other than the standard one, to cope with plasma limited phases, i.e. when the plasma interacts with the inner wall. The limiter layout is presented with the aim of discussing its manufacturability and performances.

The qualification activities related to the Copper-Chromium-Zirconium (CuCrZr)-Inconel weldings, by means of EB, were also performed and are discussed in this paper, in order to manufacture the transitions – up to the steel lids – located at the ends of the limiter modules – nearby the divertor region.

For the manufacturing solutions, destructive and non-destructive tests have been carried out on the mock-ups to assess the feasibility of the technological processes, and the results are presented in this contribution.

查看原文本刊更多论文

托卡马克转向器试验装置第一壁的设计和制造鉴定活动现状

本文概述了位于罗马弗拉斯卡蒂（Frascati）的Enea研究中心正在建设的托卡马克导流器试验设施（DTT）第一墙（FW）的当前设计，以及与FW小型模型制造过程相关的资格认证活动。概述的主要目的是根据DTT设备的内板（IFW）和外板（OFW）方面的物理和DTT系统接口的许多限制，说明FW组件设计的最新版本。针对FW初步小尺寸样机制造过程中涉及的鉴定活动，对不同技术进行了比较。对于OFW等离子体表面单元（PFUs），研究了TIG、激光和电子束（EB）加工和焊接工艺作为传统的制造解决方案。选择性激光熔化增材制造技术被认为是一种有价值的工艺，它在可制造性、性能和成本之间取得了最佳的折衷。关于IFW，要制造和合格的小型模型涉及限制器模块。它将被采用，而不是标准的，以应付等离子体的有限相，即当等离子体与内壁相互作用。给出了限位器的布局，讨论了限位器的可制造性和性能。本文还进行了铜铬锆(CuCrZr)-铬镍铁合金焊接的鉴定工作，并对其进行了讨论，目的是在导流器区域附近的限位器模块末端制造过渡部分（直至钢盖）。对于制造解决方案，对模型进行了破坏性和非破坏性试验，以评估技术过程的可行性，并在本报告中介绍了结果。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.