Hydraulic analysis of the DTT divertor module

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

Fusion Engineering and Design Pub Date : 2025-06-14 DOI:10.1016/j.fusengdes.2025.115234

Davide Caprini , Morena Angelucci , Emanuela Martelli , Fabio Crescenzi , Francesco Giorgetti , Nicola Massanova , Pietro Vinoni , Domenico Marzullo , Selanna Roccella

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引用次数: 0

Abstract

Understanding coolant flow behaviour in the divertor module is critical for managing the high thermal loads encountered in Tokamak plasma scenarios. Effective cooling ensures system integrity, optimal performance, and prolonged component lifetime, especially in high-heat flux environments. This study investigates the hydraulic performance of the DTT (Divertor Tokamak Test) divertor module, focusing on achieving uniform flow distribution.

The DTT facility, under construction at ENEA C.R. Frascati, is designed to explore power exhaust solutions for DEMO. The initial DTT divertor comprises 54 water-cooled modules, each handling a total mass flow rate of 577 kg/s with water temperatures ranging here considered from 30 °C to 74 °C. Each module includes an Outer Target (OT), Inner Target (IT), and Central Target (CT), with coolant entering through an outboard manifold and flowing through nine OT tubes. Two of the external pipes return directly to the outlet manifold, while the remaining pipes continue through additional components, necessitating calibrated orifices to achieve balanced flow distribution.

A Computational Fluid Dynamics (CFD) model was developed to optimize orifice sizing in OT pipes and evaluate flow uniformity. Sensitivity analyses assessed the effects of bulk water temperature variations and manufacturing tolerances on orifice dimensions. The model also examined total pressure drops and localized losses caused by twisted tapes in the tubes promoting flow swirling. Finally, the impact of flow rate fluctuations on critical heat flux was analysed, offering insights into the hydraulic system robustness under variable conditions. Simulations were performed using ANSYS software, providing an evaluation of the divertor module cooling performance.

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DTT转向器模块的水力分析

了解导流器模块中的冷却剂流动行为对于管理托卡马克等离子体场景中遇到的高热负荷至关重要。有效的冷却确保系统的完整性，最佳的性能，并延长组件的使用寿命，特别是在高热流环境。本研究对DTT （Divertor Tokamak Test）导流器模块的水力性能进行了研究，重点是实现流量均匀分布。位于ENEA C.R. Frascati的DTT设施正在建设中，旨在探索DEMO的动力排气解决方案。最初的DTT转向器包括54个水冷模块，每个模块的总质量流量为577 kg/s，水温范围为30°C至74°C。每个模块包括外部目标（OT），内部目标（IT）和中央目标（CT），冷却剂通过外部歧管进入，流经九个OT管。两个外部管道直接返回到出口歧管，而其余的管道继续通过额外的组件，需要校准的孔来实现平衡的流量分配。建立了计算流体动力学（CFD）模型，用于优化OT管孔板尺寸和评估流动均匀性。敏感性分析评估了总体水温变化和制造公差对孔板尺寸的影响。该模型还检查了管内扭曲带促进流动旋流引起的总压降和局部损失。最后，分析了流量波动对临界热流密度的影响，为液压系统在可变条件下的鲁棒性提供了见解。利用ANSYS软件进行了仿真，对导流器模块的冷却性能进行了评估。

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.