Infrared spectral emissivities of CN-HCCB-TBM structural materials

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-11-15 DOI:10.1016/j.fusengdes.2024.114710

Leran Liu , Guoping Yang , Junshan Wan , Hongbin Liao , Jialin Gong , Xinghua Wu , Longfei Li , Yufang Liu , Zaixin Li , Long Zhang , Xiaoyu Wang

引用次数: 0

Abstract

The Infrared spectral emissivity tests were conducted from 523 K to 923 K and from 473 K to 873 K on Chinese low-activation ferritic/martensitic steel (CLF-1) and 316L(N)-IG, separately to support radiation heat transfer analysis of the Chinese Helium-Cooled Ceramic Breeder Test Blanket Module (CN-HCCB-TBM) and improve fusion-materials database. A rapid emissivity test method was utilised. The total hemispherical emissivities of these two materials were calculated using numerical integration, with values of 0.16 (523 K), 0.19 (623 K), 0.21 (723 K), 0.23 (823 K), and 0.26 (923 K) found for CLF-1, and 0.10 (473 K), 0.13 (573 K), 0.14 (673 K), 0.14 (773 K), and 0.15 (873 K) found for 316L(N)-IG. A comparison of the emissivity results for CLF-1 and Eurofer97 showed that they were in agreement.

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CN-HCCB-TBM 结构材料的红外光谱发射率

对中国低活化铁素体/马氏体钢（CLF-1）和 316L(N)-IG分别进行了 523 K 至 923 K 和 473 K 至 873 K 的红外光谱发射率测试，以支持中国氦冷却陶瓷增殖体试验毯模块（CN-HCCB-TBM）的辐射传热分析，并改进聚变材料数据库。采用了快速发射率测试方法。通过数值积分计算了这两种材料的总半球发射率，发现 CLF-1 的值分别为 0.16 (523 K)、0.19 (623 K)、0.21 (723 K)、0.23 (823 K) 和 0.26 (923 K)，而 CLF-1 的值分别为 0.对 CLF-1 和 Eurofer97 的发射率结果进行比较后发现，它们是一致的。

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.