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低温堆中间回路循环泵隔振设计研究

杜国伟 王晓欣 李笑天 宋宇 张亚军

原子能科学技术2018,Vol.52Issue(3):459-466,8.
原子能科学技术2018,Vol.52Issue(3):459-466,8.DOI:10.7538/yzk.2017.youxian.0334

低温堆中间回路循环泵隔振设计研究

Design of Vibration Isolation System for Pump in Intermediate Circuit System of Nuclear Heating Reactor

杜国伟 1王晓欣 1李笑天 1宋宇 1张亚军1

作者信息

  • 1. 清华大学核能与新能源技术研究院,先进核能技术协同创新中心,先进反应堆工程与安全教育部重点实验室,北京 100084
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摘要

Abstract

When nuclear heating reactor (NHR) is used as marine nuclear reactor,low rpm frequency conversion pump (FCP) is used in the intermediate circuit system (ICS).The vibration isolation system of FCP was studied in this paper.The effects of pipe stiffness on the natural frequencies of the system were studied through theoretical derivation and the ranges of vibration isolator parameters which ensure the pumps to operate normally were determined.Furthermore,the performance of isolation systems with various types and parameters was studied using finite element method.The design method of a qualified vibration isolation system for low rpm FCPs was presented.The results show that when the isolators are properly chosen for FCPs in the ICS,the natural frequencies of the isolation system are kept away from those of the pumps.Meanwhile,the isolation performance is satisfactory.

关键词

低温堆/低转速变频泵/固有频率/隔振系统/振级落差

Key words

nuclear heating reactor/low rpm frequency conversion pump/natural frequency/vibration isolation system/vibration level difference

分类

能源科技

引用本文复制引用

杜国伟,王晓欣,李笑天,宋宇,张亚军..低温堆中间回路循环泵隔振设计研究[J].原子能科学技术,2018,52(3):459-466,8.

基金项目

国家自然科学基金资助项目(11302116) (11302116)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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