用于地震和LB LOCA评估的VVER-1000反应堆动态模型

Oleksii Ishchenko, V. Filonov, Y. Dubyk
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引用次数: 0

摘要

基于乌克兰核电站的经验,对VVER-1000反应堆的地震和动力强度进行了评估,重点是燃料组件的相互作用。燃料组件结构对外部作用力响应的评估基于NUREG-800“标准评审计划”第4.2项“燃料系统设计”。分析考虑了两种类型的事件:安全停机地震(SSE)和冷却剂大断裂损失事故(LB LOCA)。考虑了VVER-1000 -“最大设计事故”再循环断线的LB LOCA。在初始动力学分析中,采用了考虑两相流的VVER-1000的三维CFD模型(ANSYS CFX)。为了考虑减压过程中相变的短暂性,提出了一种特殊的相间交换模型,该模型不仅考虑了非平衡温度,而且将压力变化的特征与空化类比。为了进行全面的动力分析,有必要建立反应器的分析和/或FEM模型,该模型将包括反应器元件,其质量,刚度和惯性特性。通过对燃油组件在非压缩和压缩工况下的固有频率实验数据进行验证,并对有无流体影响的工况进行了验证。地震分析考虑了核电站场址在SSE级三分量地震影响下的可用反应谱。另一个重要的问题是分析反应堆元件的相互作用,并在需要时解释模型的非线性行为。通过考虑整个反应堆系统的动态响应,计算了燃料组件固定位置(上下支撑板)的地震和LOCA冲击。在演示了燃料组件和反应堆内部的地震/动力稳定性之后,给出了在两种载荷下保持燃料组件安全系数的合理结论。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation
The assessment of seismic and dynamic strength for the VVER-1000 reactor with emphasis on fuel assemblies interaction is carried out based on experience for Ukrainian NPPs. Evaluation of fuel assembly structural response to externally applied forces is based on NUREG-800 “Standard Review Plan”, item 4.2 “Design of fuel systems”. The analysis considered two types of events: Safety Shutdown Earthquake (SSE) and Large break Loss Of Coolant Accident (LB LOCA). As LB LOCA for the VVER-1000 – “Maximum design accident” Recirculation Line Break is considered. For the analysis of the initial dynamics, the 3D CFD model (ANSYS CFX) of the VVER-1000 was adapted to account for the two-phase flow. To take into account the transience of the phase transition during depressurization, a special model of interphase exchange is proposed, which takes into account not only the nonequilibrium temperature, but also the features of the pressure change by analogy with cavitation. For full dynamic analysis, it is necessary to develop an analytical and/or FEM model of the reactor, which will include reactor elements, their masses stiffness and inertia characteristics. The developed model is validated against experimental data of natural frequencies of fuel assembles, for uncompressed and compressed working position, also with and without fluid influence. The seismic analysis consider the available response spectra for NPP site with 3-component seismic impact of SSE level. Another important issue is to analyze reactor elements interaction and in case of need, to account for the non-linear behavior of the model. The seismic and LOCA impact at the location of fixation of the fuel assemblies (lower and upper support plates) is calculated by taking into account the dynamic response of the reactor system as a whole. After demonstrating the seismic/dynamic stability of the fuel assemblies and the reactor internals, a justified conclusion is provided on preserving the safety factor for fuel assembles at both loadings.
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