The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool

World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering Pub Date : 2016-04-06 DOI:10.5281/ZENODO.1124612

J. R. Wang, H. T. Lin, Y. Tseng, W. Y. Li, H. C. Chen, S. W. Chen, C. Shih

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Abstract

TRACE is developed by U.S. NRC for the nuclear power plants (NPPs) safety analysis. We focus on the establishment and application of TRACE/FRAPTRAN/SNAP models for Chinshan NPP (BWR/4) spent fuel pool in this research. The geometry is 12.17 m × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are three TRACE/SNAP models: one-channel, two-channel, and multi-channel TRACE/SNAP model. Additionally, the cooling system failure of the spent fuel pool was simulated and analyzed by using the above models. According to the analysis results, the peak cladding temperature response was more accurate in the multi-channel TRACE/SNAP model. The results depicted that the uncovered of the fuels occurred at 2.7 day after the cooling system failed. In order to estimate the detailed fuel rods performance, FRAPTRAN code was used in this research. According to the results of FRAPTRAN, the highest cladding temperature located on the node 21 of the fuel rod (the highest node at node 23) and the cladding burst roughly after 3.7 day.

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青山核电站乏燃料池TRACE/FRAPTRAN模型的建立与分析

TRACE是美国核管理委员会为核电厂安全分析而开发的。本研究重点研究了青山核电站(BWR/4)乏燃料池的TRACE/FRAPTRAN/SNAP模型的建立与应用。乏燃料池的几何尺寸为12.17米× 7.87米× 11.61米。在本研究中，TRACE/SNAP模型有三种:单通道、双通道和多通道TRACE/SNAP模型。并利用上述模型对乏燃料池冷却系统故障进行了仿真分析。分析结果表明，在多通道TRACE/SNAP模型下，熔覆温度峰值响应更为准确。结果表明，燃料泄漏发生在冷却系统失效后的第2.7天。为了对燃料棒的详细性能进行估计，本研究使用了FRAPTRAN代码。根据FRAPTRAN的结果，包层温度最高位于燃料棒的第21节点(第23节点最高)，大约在3.7天后包层破裂。

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World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering

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