MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS

被引：24

作者：

Park, Jong-Beom ^{[1
]}

Choi, Youngin ^{[1
]}

Lee, Sang-Jeong ^{[1
]}

Park, No-Cheol ^{[1
]}

Park, Kyoung-Su ^{[2
]}

Park, Young-Pil ^{[1
]}

Park, Chan-Il ^{[3
]}

机构：

[1] Yonsei Univ, Dept Mech Engn, Seoul 120749, South Korea

[2] Gachon Univ, Dept Mech Engn, Songnam 461701, Gyeonggi Do, South Korea

[3] Korea Inst Nucl Safety, Taejon 305338, South Korea

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2014年 / 46卷 / 05期

关键词：

Reactor Internals; Scaled-down Model; Fluid-structure Interaction; Finite Element Method; Commercial Reactor; DYNAMIC CHARACTERISTICS; CIRCULAR PLATES; VIBRATION; CONTACT;

D O I：

10.5516/NET.09.2014.017

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：

Reactor internals are sensitive to dynamic loads such as earthquakes and flow induced vibration. Thus, it is essential to identify the dynamic characteristics to evaluate the seismic integrity of the structures. However, a full-sized system is too large to perforni modal experiments, making it difficult to extract data on its modal characteristics. In this research, we constructed a finite element model of the APR1400 reactor internals to identify their modal characteristics. The commercial reactor was selected to reflect the actual boundary conditions. Our FE model was constructed based on scale-similarity analysis and fluid-structure interaction investigations using a fabricated scaled-down model.

引用

页码：689 / 698

页数：10

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