热时效对CLAM钢中氘渗透和保留行为的影响

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

Fusion Engineering and Design Pub Date : 2025-06-24 DOI:10.1016/j.fusengdes.2025.115268

Zongming Shao , Hao Yang , Siwei Zhang

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引用次数: 0

摘要

中国低活化马氏体钢作为核聚变反应堆的候选结构材料之一，其性能在高温下逐渐退化。热时效对CLAM钢力学性能的影响已经得到了广泛的研究，但热时效后CLAM钢中氘的渗透和保留行为尚不清楚。在本研究中，CLAM钢在923 K中暴露8000 h，随后进行热解吸光谱（TDS）和气驱渗透（GDP）实验，研究热老化后CLAM钢中氘的渗透和保留的演变。结果表明：经过8000 h热时效处理后，CLAM钢中的氘潴留量降低，而氘的渗透率提高；进一步的显微组织表征表明，在热时效过程中，作为氘捕获位点的位错演化为亚晶界。晶界作为氘原子的快速扩散路径，导致渗透增加和保留减少。

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Influence of thermal aging on the deuterium permeation and retention behavior in the CLAM Steel

As one of the candidate structural materials for the fusion reactor, the properties of China Low Activation Martensitic (CLAM) steel gradually degrade during service at high temperature. While the effects of thermal aging on the mechanical properties of CLAM steel have been widely studied, the behavior of deuterium permeation and retention in CLAM steel after thermal aging is not yet well understood. In this study, the CLAM steel was exposed to 923 K for 8000 h. Subsequently, thermal desorption spectroscopy (TDS) and gas-driven permeation (GDP) experiments were performed to investigate the evolution of deuterium permeation and retention in CLAM steel following thermal aging. The results showed that the deuterium retention in CLAM steel decreased after thermal aging for 8000 h, while the deuterium permeability of aged CLAM steel increased. The further microstructural characterization reveals that dislocations, which serve as deuterium trapping sites, evolve into sub-grain boundaries during the thermal aging process. The grain boundaries, acting as rapid diffusion paths for deuterium atoms, lead to an increase in permeation and a decrease in retention.

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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.