Transient numerical analysis of steam generator thermal hydraulics during down load process

ZHENG Lusong; ZHAO Yingjie; SUN Baozhi; QI Hongliang

doi:10.11949/j.issn.0438-1157.20151115

您当前的位置：

首页 >

文章列表页 >

Transient numerical analysis of steam generator thermal hydraulics during down load process

更新时间：2025-12-10

- Transient numerical analysis of steam generator thermal hydraulics during down load process
- CIESC Journal Issue S2, Pages: 116-122(2015)
- 作者机构：
  
  1. 哈尔滨工程大学动力与能源工程学院,黑龙江,哈尔滨,150001
  2. 中国船舶重工集团公司第703研究所广翰燃机事业部,黑龙江,哈尔滨,150001
- 作者简介：
- 基金信息：
- DOI：10.11949/j.issn.0438-1157.20151115
  CLC： L33
- Online First：31 August 2015，
  
  Published：31 August 2015
- 稿件说明：
移动端阅览
ZHENG Lusong, ZHAO Yingjie, SUN Baozhi, et al. Transient numerical analysis of steam generator thermal hydraulics during down load process[J]. CIESC Journal, 2015, (S2): 116-122.
DOI：

ZHENG Lusong, ZHAO Yingjie, SUN Baozhi, et al. Transient numerical analysis of steam generator thermal hydraulics during down load process[J]. CIESC Journal, 2015, (S2): 116-122. DOI： 10.11949/j.issn.0438-1157.20151115.

摘要

基于大亚湾核电站蒸汽发生器实际运行过程

采用CFD技术

对其100%~50%工况的降负荷过程进行瞬态模拟

以揭示蒸汽发生器流动传热特性在降负荷过程中的动态变化规律。计算结果表明

降负荷过程中

一、二次侧流体热工参数均随时间降低

而且随着换热强度下降

支撑板(TSPs)对二次侧含汽率、流速及表面换热系数的扰动作用也逐渐减弱。对应于100%、70%及50%三种工况

一次侧流体出口温度分别为297.2、295.6和294.8℃

二次侧出口流体平均质量含汽率分别为24.5%、16.7%和12.1%

模拟结果均与大亚湾核电站运行过程中的实际值相符。研究结果为蒸汽发生器的安全运行及优化设计提供了理论参考。

Abstract

Based on the actual operating process of the steam generator in Daya Bay Nuclear Power Plant

a transient simulation of load down from 100% to 50% operating condition was carried out by utilizing the CFD technologies to reveal the dynamic variation rule of steam generator heat-transfer characteristics in the load down process.The simulation results show that fluid thermal parameters of the primary and secondary sides decrease over time in the load down process.With the decrease of heat transfer intensity

the perturbation impact of tube support plates(TSPs)on steam quality

fluid velocity

and surface heat transfer coefficient in the secondary side decrease gradually.Corresponding to the operating condition of 100%

70% and 50%

the fluid temperature of primary outlet is 297.2

295.6 and 294.8℃ and the steam quality at the outlet of secondary outlet is 24.5%

16.7% and 12.1%

respectively

which are in consistent with actual operating parameters of steam generator in Daya Bay Nuclear Power Plant.These results can provide theoretical support to the safe operation and optimization design of steam generator.

关键词

Keywords

references

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Study on enhanced pool boiling heat transfer based on self-driven jet device

Numerical simulation for flow condensation of methanol in horizontal tube

Model development and validation of structural two-fluid model for heat transfer in a gas-solid bubbling fluidized bed

Visualization study on a nitrogen pulsating heat pipe under different condenser temperatures

Research progress on basic theory and improvement technology for critical heat flux of microchannel

Related Author

SU Zeshi

GAO Ming

ZUO Qirong

DONG Wuhan

GUO Jiangyue

CHANG Shoujin

HU Haitao

ZHAO Jinpeng

Related Institution

School of Energy and Power Engineering, University of Shanghai for Science and Technology

School of Mechanical Engineering, Shanghai Jiao Tong University

State Key Laboratory of Heavy Oil Processing, China University of Petroleum

State Key Laboratory of Multiphase Complex Systems, Institute of Process Engineering, Chinese Academy of Sciences

School of Chemical Engineering, University of Chinese Academy of Sciences

⁰