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

Han ZHANG; Tao ZHOU; Xiaorui TIAN; Lanyu ZHOU; Bangyang XIA

doi:10.11889/j.0253-3219.2018.hjs.41.020601

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

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Numerical simulation of particulate matter injection in the steam generator tube rupture accident
  封面论文
- NUCLEAR TECHNIQUES Vol. 41, Issue 2, Article number: 020601(2018)
- 作者机构：
  
  1.华北电力大学核科学与工程学院北京 102206
  2.华北电力大学核热工安全与标准化研究所北京 102206
  3.华北电力大学非能动核能安全技术北京市重点实验室北京 102206
  4.南华大学核科学技术学院衡阳 421001
  5.核反应堆系统设计技术国家级重点实验室成都 610041
- 作者简介：
- 基金信息：
  
  National Natural Science Foundation of China;Doctoral Fund of Ministry of Education of China;Foundation of Key Laboratory of Nuclear Reactor System Design Technology
- DOI：10.11889/j.0253-3219.2018.hjs.41.020601
  CLC： TL334
- Received：23 March 2017，
  
  Revised：25 April 2017，
  
  Published：10 February 2018
- 稿件说明：
移动端阅览
Han ZHANG, Tao ZHOU, Xiaorui TIAN, et al. Numerical simulation of particulate matter injection in the steam generator tube rupture accident[J]. Nuclear techniques, 2018, 41(2): 020601
DOI：

Han ZHANG, Tao ZHOU, Xiaorui TIAN, et al. Numerical simulation of particulate matter injection in the steam generator tube rupture accident[J]. Nuclear techniques, 2018, 41(2): 020601 DOI： 10.11889/j.0253-3219.2018.hjs.41.020601.

摘要

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；在破口上方及背离破口的管道附近存在颗粒物聚集现象，可能导致传热恶化；随着高度的增加，破口的影响开始扩散。

Abstract

Background

Corrosive particulate matter in 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 at Daya 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 variation in the rectangular channel

and mixture model was selected as multiphase model to conduct phase transformation

and the discrete particle model (DPM) was used to track the trajectory of the particulate matter.

Results

The high-temperature speed and concentration field in SGTR appeared near the rupture tube

which would become homogeneous above the tube. There was reflux over the rupture

inducing the particulate matter to flow with the fluid

which would impact the wall of the secondary side

especially that near the rupture tube. Particulate matter aggregation occurs above and back of rupture tube

which might cause deterioration of heat transfer. With the increase of altitude

the influence of the rupture began to diffuse.

Conclusion

It is shown that when there is a steam generator tube rupture accident

the particles can cause abrasion on the wall surface and accelerate corrosion with the movement of flow field.

关键词

Keywords

references

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