蒸汽传热管破裂事故中颗粒物喷射的数值模拟

张晗; 周涛; 田晓瑞; 周蓝宇; 夏榜样

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

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蒸汽传热管破裂事故中颗粒物喷射的数值模拟

核能科学与工程 | 更新时间：2021-05-19

- 蒸汽传热管破裂事故中颗粒物喷射的数值模拟
  封面论文
- Numerical simulation of particulate matter injection in the steam generator tube rupture accident
- 核技术 2018年41卷第2期文章编号：020601
- 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：
  
  [ "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", "ZHANG Han, male, born in 1993, graduated from Hebei University of Science and Technology in 2015, master student, focusing on nuclear power thermal hydraulic" ]
  周涛, E-mail:zhoutao@ncepu.edu.cnZHOU Tao, E-mail: zhoutao@ncepu.edu.cn
- 基金信息：
  
  国家自然科学基金(50976033);教育部博士点基金(200800791005);核反应堆系统设计技术重点实验室基金(2015BJ0151)
- DOI：10.11889/j.0253-3219.2018.hjs.41.020601
  中图分类号： TL334
- 收稿日期：2017-03-23，
  
  修回日期：2017-04-25，
  
  纸质出版日期：2018-02-10
- 稿件说明：
移动端阅览
张晗, 周涛, 田晓瑞, 等. 蒸汽传热管破裂事故中颗粒物喷射的数值模拟[J]. 核技术, 2018,41(2):020601

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
张晗, 周涛, 田晓瑞, 等. 蒸汽传热管破裂事故中颗粒物喷射的数值模拟[J]. 核技术, 2018,41(2):020601 DOI： 10.11889/j.0253-3219.2018.hjs.41.020601.

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

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