FAULTS OF PNEUMATIC CUT-OFF VALVES AND DIAGNOSIS THEREOF WITH FRATOL

doi:10.19666/j.rlfd.2002.01.020

English Version Reader LoginJournal Login

您当前的位置：

首页 >

文章列表页 >

FAULTS OF PNEUMATIC CUT-OFF VALVES AND DIAGNOSIS THEREOF WITH FRATOL

更新时间：2025-09-28

- FAULTS OF PNEUMATIC CUT-OFF VALVES AND DIAGNOSIS THEREOF WITH FRATOL
- Thermal Power Generation Issue 1, Pages: 47-50(2002)
- 作者机构：
  
  1. 大亚湾核电站
  3. ,广东,深圳,518124
- 作者简介：
- 基金信息：
- DOI：10.19666/j.rlfd.2002.01.020
  CLC： TH138.52
- Published：2002
- 稿件说明：
移动端阅览
FAULTS OF PNEUMATIC CUT-OFF VALVES AND DIAGNOSIS THEREOF WITH FRATOL[J]. Thermal power generation, 2002, (1): 47-50.
DOI：

FAULTS OF PNEUMATIC CUT-OFF VALVES AND DIAGNOSIS THEREOF WITH FRATOL[J]. Thermal power generation, 2002, (1): 47-50. DOI： 10.19666/j.rlfd.2002.01.020.

摘要

大亚湾核电站使用了大量的由SEREG厂家生产的气动隔膜阀 (失气关式 )

由于其性能可靠

一般在核级要求比较高的系统上作为隔离阀使用。为了跟踪设备的运行状况

采用了 2套先进的校验测试工具FRATOLⅢH对阀门进行测试。该工具的测试可在现场进行

不需要解体阀门。通过对阀门的初始落座力、盘根力、弹簧垫片的性能等参数的测试

可对阀门的状态进行诊断

并作适当的调整。另外

还可以判断弹簧、隔膜、O形圈等备件是否需要更换

以及在减少不必要拆卸的情况下进行预防性维修。

Abstract

A lot of pneumatic diaphragm valves （lose-air to close） made by SEREG is used in Dayabay Nuclear Power Station. Because of their stable performance

these valves are used as isolation valves in the system of higher nuclear level. In order to track the operating conditions of equipment

two sets of advanced tool

FRATOL Ⅲ H

have been purchased for testing said valves. The test can be done on site without dismounting the valve. According to the measured mechanical parameters

such as the initial drop-seat load

the packing load

and the performance of spring washers

the valve state can be diagnosed and adjusted properly. In addition

the defects of spring washers

diaphragms and O-rings can be also checked with the said tool

enabling the replacement of them to be timely realized. In other words

the preventive maintenance can be implemented on the basis of reducing unnecessary disassembly.

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

XU Zhibin

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