Several mechanical problems in high temperature gas-cooled reactor

被引：0

作者：

Yu, SY ^{[1
]}

Zhang, ZM ^{[1
]}

Li, XT ^{[1
]}

Luo, XW ^{[1
]}

Li, HY ^{[1
]}

机构：

[1] Tsing Hua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China

来源：

PROCEEDINGS OF THE CHINA ASSOCIATION FOR SCIENCE AND TECHNOLOGY, VOL 1, NO 1 | 2004年

关键词：

high temperature gas-cooled reactor; structural mechanics; reactor technology;

D O I：

暂无

中图分类号：

Q [生物科学];

学科分类号：

07 ; 0710 ; 09 ;

摘要：

The nuclear power industry promotes the development of structural mechanics and forms the Structural Mechanics in Reactor Technology (SMiRT) which has its own characteristic. The Institute of Nuclear and new Energy Technology (INET) in Tsinghua University has nearly 40 years of nuclear engineering experience. A 10MW experimental High Temperature gas-cooled Reactor (HTR-10) had been established in INET at the end of 2000. This paper will put forward some problems in SMiRT that we had encountered during the HTR-10 construction. These problems include: Soil-Structure Interaction; Flow-Induced Vibration; Leak-Before-Break Analysis of the Pressurized Equipment; Issues on Nuclear Graphite Structural Mechanics; Research on Graphite Dust. Mutual research will be expected.

引用

页码：256 / 261

页数：6

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