DISPOSAL OF ABNORMAL PROBLEM FOR HP-ROTOR'S SHRINKAGE MOVEMENT IN TURBINE NO.1 OF DAYABAY NUCLEAR POWER STATION

LI Peng-ju(Pingwei Power Generation Co Ltd

doi:10.19666/j.rlfd.2007.04.018

English Version Reader LoginJournal Login

您当前的位置：

首页 >

文章列表页 >

DISPOSAL OF ABNORMAL PROBLEM FOR HP-ROTOR'S SHRINKAGE MOVEMENT IN TURBINE NO.1 OF DAYABAY NUCLEAR POWER STATION

更新时间：2025-09-28

- DISPOSAL OF ABNORMAL PROBLEM FOR HP-ROTOR'S SHRINKAGE MOVEMENT IN TURBINE NO.1 OF DAYABAY NUCLEAR POWER STATION
- Thermal Power Generation Issue 4, Pages: 69-70(2007)
- 作者机构：
  
  平圩发电有限责任公司
- 作者简介：
- 基金信息：
- DOI：10.19666/j.rlfd.2007.04.018
  CLC： TM623
- Published：2007
- 稿件说明：
移动端阅览
LI Peng-ju(Pingwei Power Generation Co Ltd. DISPOSAL OF ABNORMAL PROBLEM FOR HP-ROTOR'S SHRINKAGE MOVEMENT IN TURBINE NO.1 OF DAYABAY NUCLEAR POWER STATION[J]. Thermal power generation, 2007, (4): 69-70.
DOI：

LI Peng-ju(Pingwei Power Generation Co Ltd. DISPOSAL OF ABNORMAL PROBLEM FOR HP-ROTOR'S SHRINKAGE MOVEMENT IN TURBINE NO.1 OF DAYABAY NUCLEAR POWER STATION[J]. Thermal power generation, 2007, (4): 69-70. DOI： 10.19666/j.rlfd.2007.04.018.

摘要

D110大修(1号机第十轮大修)时通过对高压缸进行全面解体检修时发现

解体时测得收缩窜动量小于设计值0.75 mm。通过有关的测量、检查、分析后

结合轴向通流间隙变化情况

决定将高压缸向后(2号轴承方向)推0.5 mm。从大修后机组的起动及运行情况来看

有效地解决了1号机高压转子收缩窜动量异常问题

确保了机组的顺利起动和安全可靠运行。

Abstract

It had been discovered through overall inspection of HP cylinder in the tenth major repair of turbine no.1 at Dayabay Nuclear Power Station that the shrinkage movement measured during dis-assemblage was less than the designed value of 0.75 mm.After related measurement

inspection

and analysis

combined with variated clearance of the axial flow passage

it is determined to push the HP cylinder backward(to direction of bearing no.2) for 0.5 mm.From situation of start-up and operation after said major repair

it can be seen that the abnormal shrinkage movement problem of HP rotor for turbine no.1 has effectively been solved

ensuring smooth start-up

as well as safe and reliable operation of the unit.

关键词

Keywords

references

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Harmfulness analysis method for double ended break in main steam pipe of high temperature gas-cooled reactor

Investigation on residual stress in dissimilar steel weld for nuclear steam generators

Genetic algorithm based dynamic sliding mode water level control for steam generators in nuclear power stations

Research on control system of voltage stabilizer pressure and liquid level in nuclear power station

大亚湾核电站汽机高压缸胀差异常波动初步分析

Related Author

QIAN Qiuyu

SHAO Jie

ZHANG Guiying

ZHU Xinwei

XU Lianyong

GE Keke

ZHANG Junbao

WU Wanqiang

Related Institution

State Nuclear Electric Power Planning Design & Research Institute

Tianjin Key Laboratory of Advanced Joining Technology

Shanghai Nuclear Engineering Research & Design Institute

Guangdong Province Key Laboratory of Efficient and Clean Energy Utilization,South China University of Technology

Guangdong Province Key Laboratory of Efficient and Clean Energy Utilization

AI问答

⁰