验证ASTERIA-SFR堆芯破坏事故分析代码冻结模型的fis试验仿真

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-01-20 DOI:10.3390/jne4010012
T. Ishizu, Hiroki Sonoda, S. Fujita
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引用次数: 0

摘要

堆芯破坏事故(cda)的机械后果是钠冷快堆的主要安全问题。一旦岩心破裂,液化的岩心物质迅速垂直和径向分散。分散的材料穿透针束和控制棒导管(crgt),然后在穿透区边缘冻结,因为热量被传递给周围的结构。这种冻结现象可以抑制燃料分散的负反应性反馈。当crgt内部由于材料冻结而发生紧密堵塞时,堆芯材料的排出会受到阻碍,从而导致堆芯熔池的形成。因此,堆芯材料的冻结现象在控制CDA的力学后果方面起着关键作用。为了验证在我们的CDA分析代码中实现的冻结模型,ASTERIA-SFR进行了THEFIS RUN#1测试的初步模拟。计算结果表明,结构壁面冻结和结皮形成是影响侵彻行为的关键现象,结构传热是影响侵彻行为的重要参数。为了重现实验中观察到的穿透长度,需要显著降低传热系数。这表明前缘的动量交换和流动状态以及传热应该很好地模拟,以预测快速发展的CDAs中的冻结现象。
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THEFIS Test Simulation to Validate a Freezing Model of ASTERIA-SFR Core Disruptive Accident Analysis Code
The mechanical consequences of core disruptive accidents (CDAs) are a major safety concern in sodium-cooled fast reactors. Once core disruption occurs, liquefied core materials rapidly disperse vertically and radially. The dispersed materials penetrate the pin bundles and control rod guide tubes (CRGTs) before freezing at the edge of the penetration zone as heat is transferred to surrounding structures. Such freezing phenomena can suppress the negative reactivity feedback of fuel dispersion. The discharge of core materials can be impeded, resulting in a molten core pool formation when tight blockages occur inside CRGTs due to frozen material. Accordingly, freezing phenomena of core materials play a key role in governing the mechanical consequences of a CDA. To validate a freezing model implemented in our CDA analysis code, ASTERIA-SFR, a preliminary simulation of the THEFIS RUN#1 test, was performed. The calculation results show that freezing on the structural wall and crust formation were key phenomena affecting the penetration behavior, and the structural heat transfer is an important parameter. A remarkable reduction of the heat transfer coefficient was required to reproduce the penetration length observed in the experiment. This suggests that the momentum exchange and flow regime at the leading edge as well as heat transfer should be well modeled to predict the freezing phenomena in rapidly evolving CDAs.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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