M.A. Vázquez-Barroso , C. Torregrosa-Martín , J. Maestre
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引用次数: 0
摘要
IFMIF-DONES 将是一个复制未来聚变反应堆预期条件的材料辐照辐射设施。它将使用一束 40 兆电子伏的氘核射束,射向以 15 米/秒速度循环的液态锂靶,产生高能中子,沉积 5 兆瓦。背板(BP)紧靠液态锂下游,将加速器和靶室的真空与容纳辐照模块的低压 He 大气隔开。在不关闭光束的情况下,液态锂帘的厚度可能会最终丧失,这就有可能导致氘核光束直接或部分撞击 BP,造成大量功率沉积。这项研究提供了 BP 的动态热机械响应,目的是确定撞击触发事件(如机械故障、熔化或汽化)的相关时间特征。这对于评估 BP 活性材料的最终挥发以及光束关闭的可用时间非常重要。该方法包括对功率沉积数据进行蒙特卡洛模拟,并将其集成到 ANSYS 的有限元模型中,以进行瞬态热分析和结构分析。结果包括熔化、汽化和机械响应的时间,这与光束足迹面积和锂射流厚度的减少有关。
Thermomechanical failure analysis of IFMIF-DONES target under off-nominal extreme conditions
IFMIF-DONES will be a radiological facility for material irradiation replicating conditions expected in future fusion reactors. It will employ a 40 MeV deuteron beam directed at a liquid Li target circulating at 15 m/s to generate high-energy neutrons, depositing 5 MW. The Back-Plate (BP), placed immediately downstream of the Li, separates the vacuum of the accelerator and target chambers from the low-pressure He atmosphere housing the irradiation modules. A critical scenario postulates an eventual loss of liquid Li curtain thickness without shutting down the beam, risking a direct or partial deuteron beam impact on the BP causing large power deposition. This study provides the BP dynamic thermomechanical response, aiming at characterizing the involved timings in the impact-triggered events, such as mechanical failure, melting or vaporization. This is important to evaluate the eventual mobilization of the BP volatilized activated material and the available timings for beam shutdown. The methodology involves Monte-Carlo simulations for power deposition data integrated into a Finite Element model in ANSYS for transient thermal and structural analyses. Results include timings for melting, vaporization, and mechanical response as function of the beam footprint area and the Li jet thickness reduction.
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.