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首页> 外文期刊>Nuclear engineering and technology >A Numerical Design and Feasibility Study of Self-Wastage Experiment Using Simulant Material in a Sodium Fast Reactor
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A Numerical Design and Feasibility Study of Self-Wastage Experiment Using Simulant Material in a Sodium Fast Reactor

机译:钠快堆中使用模拟材料进行自流失实验的数值设计和可行性研究

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A sodium–water reaction takes place when high-pressured water vapor leaks into sodium through a tiny defect on the surface of the heat transfer tube in a steam generator of the sodium-cooled fast reactor. The sodium–water reaction brings deterioration of the mechanical strength of the heat transfer tube at the initial leakage site. As a result, it damages the crack itself, which may eventually enlarge into a larger opening. This self-enlargement is called “self-wastage phenomenon.” In this study, a simulant experiment was proposed to reproduce the self-enlargement of a crack and to evaluate the mechanism of the self-wastage. The damage on the surface of the crack was simulated by making the neutralization reaction with hydrochloric acid solution and sodium hydroxide solution. A numerical investigation was carried out to validate the feasibility of the approach and to determine experimental conditions. From the computation results, it is observed that when 5M HCl is injected into 5M of NaOH with 0.05?m/s inlet velocity, the temperature at the surface near the crack increased over 319.26?K. The computational results show that the self-wastage phenomenon is capable of being reproduced by the simulant experiment.
机译:当高压水蒸气通过钠冷快堆蒸汽发生器中传热管表面的微小缺陷泄漏到钠中时,就会发生钠水反应。钠水反应使传热管在初始泄漏点的机械强度降低。结果,它会损坏裂纹本身,最终可能会扩大成更大的开口。这种自我扩大被称为“自我浪费现象”。在这项研究中,提出了一个模拟实验来再现裂纹的自我扩大并评估自我浪费的机理。通过用盐酸溶液和氢氧化钠溶液进行中和反应来模拟裂纹表面的损伤。进行了数值研究,以验证该方法的可行性并确定实验条件。从计算结果可以看出,当以0.05?m / s的入口速度将5M HCl注入5M NaOH中时,裂纹附近表面的温度升高到319.26?K以上。计算结果表明,模拟实验能够再现自耗现象。

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