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A comparative study of bifurcation characteristics in single and two-zone fuel models of a BWR: A case study of the advanced heavy water reactor (AHWR)

机译:BWR单区和两区燃料模型中分叉特性的比较研究:以先进重水反应堆(AHWR)为例

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A simplified nuclear-coupled thermal-hydraulic model following lumped-parameter approach is presented in which radial heat transfer modeling is refined by dividing the fuel pellet into two concentric rings (two distinct zones). Two different approaches to get the boundary between the two zones have been employed which essentially alter the heat capacities of the two zones of the fuel rod and give rise to development of two different versions of the two-zone model. Employing parameters relevant to an advanced heavy water reactor (AHWR), a comparison between the two-zone fuel model and a single-zone fuel model (Verma et al., 2016) shows that a two-zone model gives a larger stability threshold. A nonlinear analysis exploiting method of multiple time scales (MMTS) indicates that two-zone models exhibit both sub- and super-critical Hopf bifurcations. These analytical findings are verified against numerical simulations. A parametric study is performed by varying relevant system parameters to study their effects on the reactor dynamics. The study suggests that refinement in the modeling of the radial fuel heat transfer leads to an improvement in linear as well as global stability threshold of the reactor dynamical system.
机译:提出了一种基于集总参数方法的简化核耦合热工水力模型,其中通过将燃料颗粒分成两个同心环(两个不同的区域)来完善径向传热模型。已经采用了两种不同的方法来获得两个区域之间的边界,这实质上改变了燃料棒的两个区域的热容量,并且引起了两个区域模型的两个不同版本的发展。利用与先进重水反应堆(AHWR)有关的参数,对两区燃料模型和单区燃料模型进行比较(Verma等人,2016),发现两区模型具有更大的稳定性阈值。多时间尺度(MMTS)的非线性分析开发方法表明,两区域模型同时显示了亚临界和超临界Hopf分支。这些分析结果已通过数值模拟验证。通过改变相关的系统参数来进行参数研究,以研究其对反应堆动力学的影响。研究表明,径向燃料传热模型的改进导致反应堆动力学系统线性和整体稳定性阈值的提高。

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