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Uncertainty quantification of steady state depeltion solution using multi-physics coupling code system based on nodal diffusion code RAST-K

delete2025-06-13
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OA
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J
Jinsu Park
Y
Yeongseok Kang
D
Deokjung Lee
DOI:10.1016/j.net.2025.103751delete
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摘要

摘要

En 中文
本研究基于基于节点扩散代码RAST-K的多物理场耦合框架,呈现了稳态耗尽模拟的不确定性量化结果。RAST-K专为压水堆的分析与优化而开发,集成了先进方法学与多样化的工程能力,始终与测量数据和商业核设计代码表现出高度一致性。通过RAST-K与子通道热工水力代码CTF及燃料性能代码FRAPCON的多物理场耦合,开展了高保真度堆芯模拟。值得注意的是,在燃料性能计算中考虑动态间隙导热率和燃料热导率退化,凸显了棒-wise燃料温度预测的差异。不确定性量化通过随机采样方法,对输入参数和核数据同时进行扰动实现。结果表明,全局反应堆设计参数(如临界硼浓度、轴向形状指数和峰值因子)的不确定性主要受核数据扰动驱动,而热工水力不确定性则受输入参数和核数据变化的共同影响。
Keyword:
Multi-physics coupling framework
Nodal diffusion code RAST-K
Uncertainty quantification
Stochastic sampling
Nuclear data and input parameter perturbation

期刊

Nuclear Engineering and Technology 封面图
Nuclear Engineering and Technology
IF:
2.6
论文数:
1.7K
被引数:
7.9K

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