Seismic design and analysis of the support system of the HTR-10 primary loop boundary components

被引：0
|
作者：
Zhang, ZM [1 ]
Wang, MZ [1 ]
He, SY [1 ]
机构：
[1] Tsing Hua Univ, Inst Nucl Energy Technol, Div Reactor Struct & Mech, Beijing 10084, Peoples R China
来源：
NUCLEAR TECHNOLOGY | 2001年 / 135卷 / 02期
关键词：
primary loop boundary components; HTGR support system; seismic analysis;
D O I：
10.13182/NT01-A3207
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The HTR-10, which now is under construction, is the first high-temperature gas-cooled reactor developed in China. The primary loop boundary components of the HTR-IO are peculiarly arranged as the reactor pressure vessel stands side by side with the steam-generator pressure vessel, and a hot-gas duct vessel connects them. This arrangement can diminish the thermal loads on the pressure vessels but can cause some new problems under seismic conditions. The design features of the support system of the HTR-IO primary loop boundary components are introduced. The procedure of seismic analysis of the support system is emphasized. Based on equivalent-static and dynamic calculations, the safety features of the support system under seismic conditions are demonstrated.
引用
收藏
页码：85 / 91
页数：7
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