Scenario feasibility and plasma controllability for Volumetric Neutron Source (VNS)

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-05-09 DOI:10.1016/j.fusengdes.2025.115053

E. Acampora , R. Ambrosino , F. Maviglia , R. Albanese , C. Bachmann , V. Di Marzo , E. Grimaldi , M. Siccinio , I. Zammuto , G. Federici

引用次数: 0

Abstract

To test the efficiency of the blanket modules in a DEMO compliant environment, EUROfusion is considering the realization of a Volumetric Neutron Source facility (VNS). VNS will be a compact device, equipped with a DEMO-scale breeding blanket, pushing the active coils and the passive structures away from the plasma. From the electromagnetic viewpoint, this results in: the increase of the coils current needed for the definition of the plasma scenario; a reduction of the plasma shape controllability; the limitation of the stabilizing effect of the passive structures. To tackle these problems, the PMU is investigating two main design options: 1) Window-frame coil configuration 2) PF-in-TF configuration. In this paper, an electromagnetic analysis of the two design options in terms of plasma scenario feasibility and plasma controllability is proposed.

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体积中子源（VNS）的场景可行性和等离子体可控性

为了在符合DEMO的环境中测试包层模块的效率，EUROfusion正在考虑实现体积中子源设施（VNS）。VNS将是一个紧凑的设备，配备一个demo级的繁殖毯，将有源线圈和无源结构推离等离子体。从电磁学的角度来看，这导致：增加线圈电流所需的等离子体场景的定义；等离子体形状可控性的降低；被动结构稳定作用的局限性。为了解决这些问题，PMU正在研究两种主要的设计方案：1)窗框线圈配置2)PF-in-TF配置。本文从等离子体场景可行性和等离子体可控性两个方面对两种设计方案进行了电磁分析。

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.