托卡马克型聚变反应堆第一壁和包层结构的完整性评估

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mohammad Alabdullah , Nasr Ghoniem
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引用次数: 0

摘要

本研究提出了一种非线性结构分析的第一墙& &;聚变核科学设施(FNSF)的包层(FW/B),旨在识别潜在的失效模式并估计组件的寿命。分析的重点是塑性应变损伤的积累,并应用断裂力学原理来评估辐射对力学性能的影响。该研究使用了降低活化铁素体/马氏体钢F82H的数据库,特别强调了辐射引起的机械性能变化。在正常和非正常运行条件下,对各种失效模式的安全系数进行了评估。研究结果表明,断裂的主要破坏模式为流动局部化破坏、热蠕变破坏和辐射致断裂韧性降低导致的快速断裂。根据目前的经验预测方法,我们估计FW/B结构在1.2 MW/m2中子壁载荷和0.25 MW/m2表面等离子体热通量条件下可能存活约一年。这些发现表明,高通量(100 - 200dpa)的影响可能没有预期的那么显著,热蠕变损伤和断裂韧性的快速退化是控制失效的主要因素。因此,迫切需要提高在500℃以上温度下的蠕变强度,并减轻随中子通量增加而导致的断裂韧性退化。此外,中子壁载荷大于5 MW/m2的紧凑型聚变能源的发展可能需要新型的结构材料,以确保其经济可行性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Integrity assessment of Tokamak-type fusion reactor First Wall and Blanket structures
This study presents a nonlinear structural analysis of the First Wall & Blanket (FW/B) of the Fusion Nuclear Science Facility (FNSF), aimed at identifying potential failure modes and estimating the component’s lifetime. The analysis focuses on the accumulation of plastic strain damage and applies fracture mechanics principles to assess the effects of radiation on mechanical properties. The study uses a database for reduced activation ferritic/martensitic steel F82H, with particular emphasis on radiation-induced changes in its mechanical properties. Safety factors for various failure modes are evaluated both at the beginning of life and after neutron irradiation under normal and off-normal operating conditions. The results indicate that the most critical failure modes are flow localization, thermal creep damage, and fast fracture due to radiation-induced reduction in fracture toughness. Based on current empirical prediction methods, we estimate that the FW/B structure will likely survive for approximately one year of operation under conditions of 1.2 MW/m2 neutron wall loading and 0.25 MW/m2 surface plasma thermal flux. These findings suggest that the effects of very high fluence (100–200 dpa) may be less significant than expected, with thermal creep damage and rapid fracture toughness degradation being the primary factors controlling failure. Therefore, there is a critical need to improve creep strength at temperatures above 500 °C and to mitigate fracture toughness degradation with increasing neutron fluence. Furthermore, the development of compact fusion energy sources with neutron wall loads greater than 5 MW/m2 may require new classes of structural materials to ensure their economic viability.
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来源期刊
Fusion Engineering and Design
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.
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