期刊论文

Numerical simulation of particulate matter injection in the steam generator tube rupture accident

Zhou, T.

中文

核技术

0253-3219

2018

41

2

55-62

10.11889/j.0253-3219.2018.hjs.41.020601

国家自然科学基金(No.50976033)、教育部博士点基金(No.200800791005)、核反应堆系统设计技术重点实验室基金(No.2015BJ0151)资助 第一作者：张晗，男，1993 年出生，2015 年毕业于河北科技大学，现为硕士研究生，研究领域为核反应堆热工水力 通信作者：周涛，E-mail: zhoutao@ncepu.edu.cn 收稿日期：2017-03-23，修回日期：2017-04-25 Supported by National Natural Science Foundation of China (No.50976033), Doctoral Fund of Ministry of Education of China (No.200800791005), Foundation of Key Laboratory of Nuclear Reactor System Design Technology (No.2015BJ0151) First author: ZHANG Han, male, born in 1993, graduated from Hebei University of Science and Technology in 2015, master student, focusing on nuclear power thermal hydraulic Corresponding author: ZHOU Tao, E-mail: zhoutao@ncepu.edu.cn Received date: 2017-03-23, accepted date: 2017-04-25

本校为其他机构

蒸汽传热管破裂事故发生时,一回路中的颗粒物随着高温高压流体一起喷射进入二次侧,会对蒸汽发生器二次侧产生冲击并加速二次侧腐蚀。根据大亚湾核电站蒸汽发生器传热管实际尺寸建模,利用FLUENT流体软件,对蒸汽传热管破裂事故发生时的颗粒物喷射过程进行模拟研究。对连续相采取k-ε模型预测湍流变化,多相流模型选择混合模型,对颗粒相采取DPM (Discrete Particle Model)模型跟踪颗粒运动轨迹。研究发现,破口附近是高速场和高温度场,而在破口上方,温度场和速度场逐渐恢复均匀性;在破口上方附近存在回流现象;破口附近颗粒随着流场运动对二次侧管壁产生冲击,破口附近壁面所受到的冲击最严重;在破口上...

[Background]Corrosive particulate matterin high-temperature and pressure fluid in the primary circuit will be injected into the secondary side with while the steam generator tube rupture accident (SGTR) occurs, which could accelerate corrosion of the secondary side. [Purpose]A model was built according to actual size of the steam generator heat transfer tube atDaya Bay nuclear power plant with the code of FLUENT adopted to simulate the injection process. [Methods]The standard k-ε model was used in continuous phase to predict the turbulence var...