压水堆核电厂管道泄漏特性数值模拟研究  

Numerical Simulation of Leakage Characteristics of Pressurized Water Reactor Nuclear Power Plant

作　　者：殷松涛 王宁宁 王海军[1] 朱梦馨 Yin Songtao;Wang Ningning;Wang Haijun;Zhu Mengxin(State Key Laboratory of Multiphase Flow in Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China)

机构地区：[1]西安交通大学能源与动力工程学院多相流国家重点实验室,西安710049

出　　处：《核动力工程》2021年第3期32-36,共5页Nuclear Power Engineering

基　　金：国家自然科学基金项目(11675128)。

摘　　要：为研究压水堆核电厂管道泄漏特性,基于一维两流体数值模型,耦合了等温气泡生长模型,提出了一种两相临界流模型,该模型考虑了临界流过程中的亚稳态流体核化与非平衡传质。该模型通过一种显式差分格式的算法加以实现。通过与相关实验数据进行对比计算可知,本文模型具有较高的计算精度与计算效率。利用该模型对两相临界流流动与传质过程进行了理论分析,结果表明,流体过冷度对流动与传质过程具有显著影响,而流体入口压力仅影响流动过程。本研究建立的两相临界流模型可为管道与压力容器泄漏安全性分析提供参考与理论基础。This paper aims to propose a two-phase critical flow model to accurately evaluate the leakage rate of pipeline breaks.The critical flow model considering the nucleation of metastable liquids and non-equilibrium mass transfer is based on a two-fluid model coupled with an isothermal bubble growth model.The model is implemented by an explicit difference algorithm.The proposed model calculates fast and the model predictions exhibit strong similarities with the experimental data.The numerical research of the leakage process for critical flow is conducted.The results show that the subcooling has a significant effect on the fluid flow and the mass transfer process,while the upstream pressure only affects the fluid flow.The proposed model can provide a theoretical basis for the safety analysis of pressurized pipelines and vessels.

关 键 词：两流体数值模型 两相临界流 核化模型 管道泄漏 

分 类 号：TL334[核科学技术—核技术及应用]