早期中子辐照F82H及其模型合金在363 K和563K下的缺陷结构演变

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Pinyao Wang , Shaosong Huang , Koichi Sato , Qiu Xu , Toshimasa Yoshiie
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引用次数: 0

摘要

了解空心膨胀孕育期的点缺陷过程对核结构材料的开发至关重要。利用正电子湮没寿命谱和跃迁电镜研究了中子辐照后Fe和6种F82H模型合金中增加Fe元素后的潜伏期缺陷结构。在363 K辐照下,在0.2 dpa的剂量下,铁和所有模型合金中都检测到空位团簇。在563 K辐照下,除Fe外,未检测到空位团簇。这些结果表明Cr对这些间隙型环在高温下长距离迁移的模式变化有影响。稳态膨胀的开始是Cr原子与Fe间隙团簇相互作用的有效数目达到饱和。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Defect structure evolution in early-stage neutron irradiated F82H and its model alloys at 363 K and 563K
To understand the point defect processes during the incubation period of the void swelling is critical for the development of nuclear structural materials. The defect structures in the incubation period in neutron irradiated Fe and 6 model alloys of F82H, increasing the elements from Fe, were studied by positron annihilation lifetime spectroscopy and transition electron microscopy. During the irradiation at 363 K, vacancy clusters were detected in Fe and all model alloys to a dose of 0.2 dpa. With 563 K irradiation, no vacancy clusters were detected except for Fe. These results suggest the effect of Cr on model change of the long-range migration of these interstitial-type loops at high temperature. The start of steady state swelling is the saturation of the effective number of Cr atoms interacting with Fe interstitial clusters.
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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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