研究暴露于氧乙炔焰的混凝土的传热和烧蚀行为的实验研究和反传热分析

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-19 DOI:10.1016/j.anucene.2024.110991
Pedduri Jayakrishna , Prakash Nanthagopalan , Arunkumar Sridharan , Shyamprasad Karagadde , Anuj Kumar Deo , Srinivasa Rao , P.K. Baburajan , S.V. Prabhu
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引用次数: 0

摘要

通过氧乙炔焊接实验研究了核反应堆周围牺牲混凝土的烧蚀现象。氧乙炔焊接产生的氧化焰是铁硅质混凝土(含赤铁矿骨料)和普通混凝土(不含赤铁矿骨料)接触到的高热流量和高温度的潜在来源。据观察,高强度氧化焰造成的烧蚀非常不均匀。与含铁混凝土相比,普通混凝土的最大温升、烧蚀深度和总体质量损失都更高。铁硅酸盐混凝土中赤铁矿的存在减少了混凝土内部的热扩散、烧蚀深度和烧蚀材料的质量,因此表现出更好的烧蚀特性。研究人员制定了一个忽略化学反应影响的半无限传热模型,并估算了火焰与混凝土界面上形成的近似界面热通量曲线。研究结果得出结论,硅铁混凝土可以承受氧化火焰的高热通量,因此可以抵御核反应堆失效时熔融铈与混凝土壁相互作用的不利情况。
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Experimental investigations and inverse heat transfer analysis to study heat transfer and ablation behaviour of concrete exposed to oxyacetylene flame
The phenomenon of ablation occurring in sacrificial concrete surrounding the nuclear reactor is studied by conducting experiments with oxyacetylene welding. The oxidizing flame produced from the oxyacetylene welding is a potential source of high heat flux and temperature exposed to the ferrosiliceous concrete (contains hematite aggregates) and ordinary concrete (without hematite aggregates). The ablation caused by the high-intensity oxidizing flame is observed to be highly non-uniform. The maximum temperature rise, ablation depths and overall mass loss in ordinary concrete are observed to be higher compared to the ferrosiliceous concrete. The presence of hematite in ferrosiliceous concrete has reduced the heat diffusion, ablation depth and mass of ablated material inside the concrete and hence exhibited better ablation characteristics. A semi-infinite heat transfer model ignoring the effects of chemical reactions are formulated and estimated the approximate interfacial heat flux profiles develop at the interface between the flame and concrete. The outcomes of the study conclude that the ferrosiliceous concrete can withstand the high heat fluxes of the oxidizing flame, and hence, it will withstand the adverse scenario of the interaction of molten corium with concrete walls occurs during the failure of nuclear reactors.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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