| 注册
首页|期刊导航|压力容器|某项目安注管线热棘轮效应分析与评定

某项目安注管线热棘轮效应分析与评定

刘雪林 王明毓 汤凤 黄飞翔

压力容器2017,Vol.34Issue(7):45-49,72,6.
压力容器2017,Vol.34Issue(7):45-49,72,6.DOI:10.3969/j.issn.1001-4837.2017.07.007

某项目安注管线热棘轮效应分析与评定

Analysis and Evaluation of Thermal Ratchet Effect on Safety Injection Pipelines of a Project

刘雪林 1王明毓 1汤凤 1黄飞翔1

作者信息

  • 1. 深圳中广核工程设计有限公司,广东深圳518057
  • 折叠

摘要

Abstract

The pressure vessels and pipelines of the nuclear reactor bears various complex load conditions such as internal pressure,circulating heat loads and vibrations during the operation of the nuclear power plant,which will cause ratcheting effect to reduce the fatigue life of the material or structure,seriously affecting the safety and reliability of the pressure vessels and pipelines.The RCC-M code about the thermal ratchet effect of the PWR nuclear power plant is based on the BREE diagram.It is found that when a pipeline is subjected to a large thermal shock transient load,it may not meets the requirements of this specification,and further analysis of the stability of the pipe ratchet is necessary.This paper analyzed the RCC-M code for the calculation formula and evaluation requirements of the pipe thermal ratchet effect.It can be found that the ratcheting effect of the pipe can be evaluated by the thin-wall cylinder approximation formula.The results show that the thermal ratcheting effect produced by cyclic thermal shock able to meet the RCC-M code requirements.The project design has a certain reference value.

关键词

热棘轮/RCC-M/热冲击

Key words

thermal ratchet/RCC-M/thermal shock

分类

机械制造

引用本文复制引用

刘雪林,王明毓,汤凤,黄飞翔..某项目安注管线热棘轮效应分析与评定[J].压力容器,2017,34(7):45-49,72,6.

压力容器

OA北大核心CSTPCD

1001-4837

访问量2
|
下载量0
段落导航相关论文