In the further development of nuclear fusion energy, managing the high heat flux on a divertor target remains a significant issue. To address this, the development of innovative cooling channels capable of efficiently managing high heat loads is essential. Among various cooling techniques, the hypervapotron (HV) method stands out for its exceptional heat transfer capabilities. This study undertakes an in-depth analysis of a novel HV cooling channel, evaluating its heat transfer performance via an electron beam high heat flux testing system. The focus was on subcooled flow boiling, observing that the novel HV channel displayed varied flow patterns with increasing heat flux. Additionally, a comparative investigation was conducted to assess the heat transfer efficiency of this novel HV channel against traditional ITER-like HV channel and smooth channel. The analysis incorporated various system parameters, such as mass flow rate and system pressure, to understand their effects on heat transfer. To effectively predict the heat transfer performance of the novel HV channel, efforts have been made to evaluate existing and develop new heat transfer correlations for the channel. Furthermore, Artificial Neural Networks (ANNs) have also been utilized as a crucial approach in this predictive endeavor. The outcomes of this study hold significant implications for understanding and optimizing the design of cooling channels for divertor target in nuclear fusion reactors.

中文翻译：

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核聚变反应堆偏滤器靶新型超汽化管传热特性实验研究

在核聚变能的进一步发展中，管理偏滤器目标上的高热通量仍然是一个重要问题。为了解决这个问题，开发能够有效管理高热负荷的创新冷却通道至关重要。在各种冷却技术中，超汽化管 (HV) 方法因其卓越的传热能力而脱颖而出。本研究对新型高压冷却通道进行了深入分析，通过电子束高热通量测试系统评估其传热性能。重点是过冷流动沸腾，观察到新型高压通道随着热通量的增加而显示出不同的流动模式。此外，还进行了比较研究，以评估这种新型高压通道与传统的类 ITER 高压通道和光滑通道的传热效率。该分析结合了各种系统参数，例如质量流量和系统压力，以了解它们对传热的影响。为了有效预测新型高压通道的传热性能，人们努力评估现有的通道传热关系并开发新的传热关系式。此外，人工神经网络（ANN）也被用作这一预测工作的关键方法。这项研究的结果对于理解和优化核聚变反应堆偏滤器靶冷却通道的设计具有重要意义。