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Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations

机译:基于回归,方差和密度的全局灵敏度方法在集成VERA-CS和BISON仿真中的应用

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Uncertainty quantification (UQ) and sensitivity analyses (SA) are performed for coupled simulations between VERA-CS, a coupled pin resolved neutron transport and subchannel thermal hydraulics code, and the fuel performance code BISON. The interface between VERA-CS and BISON is performed in a multiphysics environment known as the LOCA Toolkit for U.S. light water reactors (LOTUS) currently under development at Idaho National Laboratory (INL). A focus is placed on using a variety of SA measures, including two regression based (Pearson and Spearman), one variance based (Sobol indices), and three moment independent measures (Delta moment independent measures with L-1, L-2, and L-infinity norms). The problem under inspection is a single assembly depletion case for three fuel cycles. The figures of merit are the minimum departure from nucleate boiling ratio (MDNBR), maximum fuel centerline temperature (MFCT), and gap conductance at peak power (GCPP). SA results show MDNBR to be linear with consistent rankings throughout the fuel cycles. MFCT is linear, but with a change in rankings at the switch from open gap to closed gap models. GCPP is nonlinear at intermediate states that coincide with the onset of contact between fuel and cladding. These nonlinear states allow for the show-casing of higher order SA measures over first order methods.
机译:在VERA-CS,耦合销分解中子传输和子通道热液力代码以及燃料性能代码BISON之间的耦合模拟中,执行不确定性量化(UQ)和灵敏度分析(SA)。 VERA-CS和BISON之间的接口是在爱达荷州国家实验室(INL)目前正在开发的称为美国轻水反应堆(LOTUS)的LOCA工具包的多物理环境中执行的。重点放在使用各种SA度量上,包括两个基于回归的(Pearson和Spearman),一个基于方差的(Sobol指数)和三个独立于矩的度量(与L-1,L-2和L-无穷大范数)。检查中的问题是一个用于三个燃料循环的单个组件耗尽情况。优值是偏离核沸腾率的最小偏差(MDNBR),最大燃料中心线温度(MFCT)和峰值功率下的气隙电导(GCPP)。 SA结果表明MDNBR是线性的,在整个燃料循环中排名一致。 MFCT是线性的,但排名从开放差距模型转换为封闭差距模型时发生了变化。 GCPP在中间状态是非线性的,该状态与燃料和包层之间的接触开始相吻合。与一阶方法相比,这些非线性状态允许显示更高阶SA度量。

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