通过锻拉工艺实现耐高温氧化的带仪表刻度的内侧保护包层

IF 4.3 3区 工程技术 Q2 ENERGY & FUELS International Journal of Energy Research Pub Date : 2024-07-05 DOI:10.1155/2024/4896959
Jeong-Hye Jo, Ji-Hyeok Choi, Jong Woo Kim, Dong-Joo Kim, Young Soo Yoon
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引用次数: 0

摘要

福岛核事故等核事故凸显了事故耐受燃料(ATF)包层的必要性。以往的研究侧重于在真空环境中为目前用于核反应堆的 Zr 合金外部镀上一层抗氧化材料。这将涂层局限于包壳内部,无法在米级包壳上实现均匀的涂层。在这项研究中,展示了一种基于室温和非真空的锻拉工艺,作为包层制造工艺的替代方案。它使 2 米长的锆合金覆层的内外两侧都均匀地覆盖了 100 微米厚的耐腐蚀材料(316-L 不锈钢;SS316L),从而最大限度地减少了高温氧化,避免了故障。经过锻拉工艺后,外层 SS316L 与 Zr 合金之间的间隙小于 1 微米,内层 Zr 合金与 SS316L 之间的间隙约为 12 微米。在大气环境中,对所生成的三重 Gachon ATF 覆层管(G-tube)的高温氧化特性进行了评估,最高温度为 1,200°C 。在 1200°C 高温下进行热处理后,对照包层完全氧化并破裂,可能导致放射性物质在应用过程中泄漏。与此相反,尽管存在间隙,但通过锻拉工艺制造的 G 型管包层只有 15% 被氧化,而且 G 型管的 Zr 合金相从 α-Zr 转变为 α-Zr (O) 和之前的 β-Zr。通过显微镜、X 射线衍射和热重分析,对包层的微观结构、氧化层和氧化机制进行了分析。结果证实,SS316L 能完全阻止氧气扩散到块状 Zr 合金中。此外,SS316L 和 Zr 合金之间没有元素扩散。这些结果证明了在极高温度下使用基于室温、非真空环境的锻拉工艺制造结构稳定的 ATF 熔覆层的可行性。
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Inner-Side-Protected Cladding with Meter Scale for High-Temperature Oxidation Resistance via the Swaging–Drawing Process

Nuclear accidents, such as the Fukushima nuclear accident, have highlighted the necessity for accident-tolerant fuel (ATF) cladding. Previous studies focused on coating the outside of Zr alloy currently used in nuclear reactors with an oxidation-resistant material in a vacuum environment. This limits the coating to the inside of the cladding and does not tend to achieve a uniform coating on meter scale cladding. In this study, a room temperature and non-vacuum-based swaging–drawing process was demonstrated as an alternative cladding manufacturing process. It enables both the inner and outer sides of the 2-m-long Zr alloy cladding to be uniformly covered with a 100-μm-thick corrosion-resistant material (316-L stainless steel; SS316L), thereby minimizing its high-temperature oxidation and avoiding failures. After the swaging–drawing process, there was a gap of less than 1 µm between outer SS316L and Zr alloy and a gap of about 12 µm between inner Zr alloy and SS316L. The high-temperature oxidation properties of the resulting triplex Gachon ATF cladding tube (G-tube) were evaluated up to 1,200°C in an atmospheric environment. Following heat treatment at 1,200°C, the control cladding completely oxidized and ruptured, potentially causing leakage of radioactive material during application. In contrast, only 15% of the G-tube cladding manufactured by the swaging–drawing process was oxidized despite a gap, and the Zr alloy of the G-tube changed phase from α-Zr to α-Zr (O) and prior β-Zr. The cladding microstructure, oxide layer, and oxidation mechanism were analyzed through microscopy, X-ray diffraction, and thermogravimetric analysis. As a result, it was confirmed that SS316L completely prevented oxygen diffusion into the bulk Zr alloy. In addition, there was no elemental diffusion between SS316L and the Zr alloy. These results demonstrate the feasibility of using room temperature, nonvacuum environment-based swaging–drawing process to fabricate structurally stable ATF cladding at extremely high temperatures.

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来源期刊
International Journal of Energy Research
International Journal of Energy Research 工程技术-核科学技术
CiteScore
9.80
自引率
8.70%
发文量
1170
审稿时长
3.1 months
期刊介绍: The International Journal of Energy Research (IJER) is dedicated to providing a multidisciplinary, unique platform for researchers, scientists, engineers, technology developers, planners, and policy makers to present their research results and findings in a compelling manner on novel energy systems and applications. IJER covers the entire spectrum of energy from production to conversion, conservation, management, systems, technologies, etc. We encourage papers submissions aiming at better efficiency, cost improvements, more effective resource use, improved design and analysis, reduced environmental impact, and hence leading to better sustainability. IJER is concerned with the development and exploitation of both advanced traditional and new energy sources, systems, technologies and applications. Interdisciplinary subjects in the area of novel energy systems and applications are also encouraged. High-quality research papers are solicited in, but are not limited to, the following areas with innovative and novel contents: -Biofuels and alternatives -Carbon capturing and storage technologies -Clean coal technologies -Energy conversion, conservation and management -Energy storage -Energy systems -Hybrid/combined/integrated energy systems for multi-generation -Hydrogen energy and fuel cells -Hydrogen production technologies -Micro- and nano-energy systems and technologies -Nuclear energy -Renewable energies (e.g. geothermal, solar, wind, hydro, tidal, wave, biomass) -Smart energy system
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