Reactor internals and hold down spring stiffness/reaction calculation

ZHANG Zhai XUE Guohong

doi:10.11889/j.0253-3219.2013.hjs.36.040608

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Reactor internals and hold down spring stiffness/reaction calculation

更新时间：2021-06-03

- Reactor internals and hold down spring stiffness/reaction calculation
- NUCLEAR TECHNIQUES Vol. 36, Issue 4, Article number: 040608(2013)
- 作者机构：
  
  上海核工程研究设计院
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2013.hjs.36.040608
  CLC： TL351.6
- Published：2013
- 稿件说明：
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[1]张翟,薛国宏.压紧弹性环的设计方案优化分析[J].核技术,2013,36(04):41-45.

ZHANG Zhai XUE Guohong. Reactor internals and hold down spring stiffness/reaction calculation[J]. Nuclear techniques, 2013, 36(4): 040608
[1]张翟,薛国宏.压紧弹性环的设计方案优化分析[J].核技术,2013,36(04):41-45. DOI： 10.11889/j.0253-3219.2013.hjs.36.040608.

ZHANG Zhai XUE Guohong. Reactor internals and hold down spring stiffness/reaction calculation[J]. Nuclear techniques, 2013, 36(4): 040608 DOI： 10.11889/j.0253-3219.2013.hjs.36.040608.

摘要

压紧弹性环位于压紧部件法兰与吊篮部件法兰之间

将吊篮结构压紧并定位于反应堆压力容器内。本文应用秦山核电站压紧弹性环组件分析时的方法

对AP1000和LPP压紧弹性环采用了解析解和数值解的计算分析方法

并对可能影响预紧分析结果的塑性变形和摩擦因素进行了探讨。最终对秦山、AP1000与LPP压紧弹性环设计方案进行了分析

提出了两种优化方案。

Abstract

Background: Hold down spring is a structural component that supports the reactor pressure vessel.It is located between the flange and barrel components

and has a function that transfers the force caused by reactor pressure vessel cap to barrel flange.Purpose: This paper attempts to have an analysis calculation and comparison of AP1000 and LPP Hold down spring.Methods: This article inherited Qinshan nuclear power hold down spring analysis method

use analytical method and FEM method to solve the problem.Results: The stress and deflection of HDS are calculated.Since the friction coefficient may have a large effect

the results of different friction coefficients are also analyzed.Conclusions: This paper compared the Qinshan

AP1000 and LPP HDS design advantages and disadvantages and proposed two kinds of new design

expected to have a reference value for follow-up engineers.

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