基于kuu - mix热工水力输入数据和CFD分析的反应堆压力容器XFEM与标准断裂力学分析Gösgen

Alexander Mutz, T. Nicak, R. Trewin, I. Cremer
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摘要

反应堆压力容器(RPV)的完整性必须按照适用的法规在其整个使用寿命期间得到保证。通常情况下,RPV抗脆性破坏的评估需要考虑所有可能的加载情况。在运行期间可能发生的最严重的负载情况之一是冷却剂丢失事故,即在运行状态下向RPV注入冷水。高压与注入冷水引起的铁素体压力容器壁的热冲击相结合,导致在带线区域产生相当大的负荷,称为加压热冲击(PTS)。通常脆性破坏的评估是基于确定性断裂力学分析,其中使用j积分或应力强度因子等常用参数来计算PTS事件中假设(假定)缺陷的载荷路径。作为这种标准方法的替代方法,可以进行基于扩展有限元法(XFEM)的断裂力学评估。断裂力学分析最重要的输入数据是应急冷却过程中反应堆的瞬态热工负荷。这些数据可以通过经过实验验证的分析流体混合代码(如kuu -mix)或经过适当验证的数值计算流体动力学(CFD)工具来计算。在PTS分析中用于TH计算的标准kuu - mix中,使用了相当保守的混合定量分析模型,并根据水位,使用了降水管中的冷凝过程(包括简化的条纹和羽流地层)。相反,数值CFD工具可以提供最好的估计结果,因为它可以更真实地考虑条纹和羽流地层以及RPV的详细几何形状。在之前的一篇论文[1]中,给出了基于kuu - mix热工液压输入数据的RPV Gösgen 1的标准和XFEM分析结果。本文提出了基于CFD热水力学输入数据的新结果。将新结果与[1]中的结果进行比较,以显示使用CFD的热工水力输入数据获得的额外安全裕度。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
XFEM and Standard Fracture-Mechanics Analyses of the Reactor Pressure Vessel Gösgen Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses
The integrity of a reactor pressure vessel (RPV) has to be ensured throughout its entire life in accordance with the applicable regulations. Typically an assessment of the RPV against brittle failure needs to be conducted by taking into account all possible loading cases. One of the most severe loading cases, which can potentially occur during the operating time, is the loss-of-coolant accident, where cold water is injected into the RPV at operating conditions. High pressure in combination with a thermal shock of the ferritic pressure vessel wall caused by the injection of cold water leads to a considerable load at the belt-line area known as Pressurized Thermal Shock (PTS). Usually the assessment against brittle failure is based on a deterministic fracture-mechanics analysis, in which common parameters like J-integral or stress intensity factor are employed to calculate the load path for an assumed (postulated) flaw during the PTS event. As an alternative to this standard approach a fracture mechanics assessments based on eXtended Finite Element Method (XFEM) approach can be performed. The most important input data for the fracture-mechanics analysis is the transient thermal-hydraulics (TH) load of the RPV during the emergency cooling. Such data can be calculated by analytical fluid-mixing codes verified on experiments, such as KWU-MIX, or by numerical Computational Fluid Dynamics (CFD) tools after suitable validation. In KWU-MIX, which is the standard used for TH calculations within PTS analyses, rather conservative analytical models for the quantification of mixing and, depending on the water level, condensation processes in the downcomer (including simplified stripe and plume formations) are utilized. On the contrary, the numerical CFD tools can provide best-estimate results due to the possibility to consider more realistically the stripe and plume formations as well as the geometry of the RPV in detail. In a previous paper [1] results of standard and XFEM analyses of the RPV Gösgen 1 based on thermal-hydraulics input data from KWU-MIX were presented. This paper presents new results based on thermal-hydraulics input data from CFD. The new results are compared with those from [1] in order to show additional safety margins obtained by using thermal-hydraulics input data from CFD.
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