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Development of cold moderator vessel for the spallation neutron source flow field measurements and thermal hydraulic analyses in cold moderator vessel

机译:开发冷缓和器容器,用于散裂中子源流场测量和冷缓和器容器中的热水力分析

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摘要

The Japan Atomic Energy Research Institute is developing a several MW-scale spallation target system under the High-Intensity Accelerator Project. A cold moderator using supercritical hydrogen is one of the key components in the target system, which directly affects the neutronic performance both in intensity and resolution. Since a hydrogen temperature rise in the moderator vessel affects the neutronic performance, it is necessary to suppress the recirculation and stagnant flows which cause hot spots. In order to develop the conceptual design of the moderator structure in progress, the flow field was measured using a PIV (Particle Image Velocimetry) system under water flow conditions using a flat model that simulated a moderator vessel. From these results, the flow field such as recirculation flows, stagnant flows etc. was clarified. The hydraulic analytical results using the standard k-ε model agreed well with experimental results. Thermal-hydraulic analyses in the moderator vessel were carried out under liquid hydrogen conditions. Based on these results, we clarified the possibility of suppressing the local temperature rise within 3K under 2MW operating condition.
机译:日本原子能研究所正在“高强度加速器项目”下开发数兆瓦规模的剥落目标系统。使用超临界氢的冷调节剂是目标系统中的关键组件之一,它直接影响中子的强度和分辨率。由于缓和容器中氢气温度的升高会影响中子的性能,因此有必要抑制引起热点的再循环和停滞流动。为了发展进行中的减速器结构的概念设计,使用PIV(颗粒图像测速)系统在水流条件下使用模拟减速器容器的平面模型来测量流场。根据这些结果,明确了再循环流,滞流等流场。使用标准k-ε模型的水力分析结果与实验结果非常吻合。在液化氢条件下在减速容器中进行热工水力分析。根据这些结果,我们阐明了在2MW的工作条件下将局部温度升高抑制在3K以内的可能性。

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