Advancements in the IFMIF-DONES target system for fusion materials irradiation

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

Fusion Engineering and Design Pub Date : 2025-06-20 DOI:10.1016/j.fusengdes.2025.115288

D. Oravecz , A. Zsákai , R.L. Csiszár , D. Ferenczy , T. Dézsi , F.S. Nitti , J. Maestre , D. Bernardi , A. Ibarra

引用次数: 0

Abstract

This paper provides an overview of the advancements in the Target System design of the IFMIF-DONES Project which simulates the effects of the extreme neutron irradiation conditions expected in the future fusion power reactors. The system’s role in generating a high-intensity neutron source for testing candidate materials to be used in the reactor is highlighted. The discussion includes design innovations, recent developments, challenges, and future prospects, emphasizing critical aspects and validation needs for the Target System.

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聚变材料辐照IFMIF-DONES靶系统的研究进展

本文概述了IFMIF-DONES项目目标系统设计的进展，该项目模拟了未来核聚变反应堆中预期的极端中子辐照条件的影响。该系统在产生高强度中子源以测试反应堆中使用的候选材料方面的作用得到了强调。讨论包括设计创新、最近的发展、挑战和未来前景，强调目标系统的关键方面和验证需求。

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.