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
收藏
页码：689 / 698
页数：10
相关论文
共 50 条
  • [41] Experiment and RELAP5 analysis for the downcomer boiling of APR1400 under LBLOCA reflood phase
    Lee, DW
    No, HC
    Lee, EH
    Oh, SJ
    Song, CH
    NUCLEAR TECHNOLOGY, 2006, 153 (02) : 175 - 183
  • [42] THE SENSITIVITY ANALYSIS FOR APR1400 NODALIZATION UNDER LARGE BREAK LOCA CONDITION BASED ON MARS CODE
    Jang, Hyung-Wook
    Lee, Sang-Yong
    Oh, Seung-Jong
    Kim, Woong-Bae
    NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2017, 32 (01): : 10 - 17
  • [43] Efficiency of various structural modeling schemes on evaluating seismic performance and fragility of APR1400 containment building
    Duy-Duan Nguyen
    Thusa, Bidhek
    Park, Hyosang
    Azad, Md Samdani
    Lee, Tae-Hyung
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (08) : 2696 - 2707
  • [44] Analysis of flow-induced vibration of nuclear reactor internals
    2016, Atomic Energy Press (37):
  • [45] Application of seismic analysis methodology to small modular integral reactor internals
    Choi, Youngin
    Park, Jongbum
    Park, No-Cheol
    Park, Young-Pil
    Park, Kyoung-Su
    Jeong, Kyeong-Hoon
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2015, 52 (02) : 228 - 240
  • [46] The APR1400 SOARCA study: Insights into the evolution of severe accidents and fission product source term analysis results
    Ahn, Kwang-Il
    Lee, Keo-hyoung
    Hwang, Seok-Won
    PROGRESS IN NUCLEAR ENERGY, 2023, 158
  • [47] Numerical investigation on seismic response of isolated APR1400 main steam pipe under optimized support direction
    Kong, Derui
    Liu, Wenguang
    Li, Zhijia
    Xu, Hao
    Zhang, Qiang
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2024, 209
  • [48] Seismic Fragility Evaluation of Main Steam Piping of Isolated APR1400 NPP Considering the Actual Failure Mode
    Jeon, Bub-Gyu
    Kim, Sung-Wan
    Yun, Da-Woon
    Hahm, Daegi
    Eem, Seunghyun
    SUSTAINABILITY, 2022, 14 (14)
  • [49] Structural assessments of plate type support system for APR1400 reactor Anh Tung Nguyen, Ihn Namgung
    Anh Tung Nguyen
    Namgung, Ihn
    NUCLEAR ENGINEERING AND DESIGN, 2017, 314 : 256 - 270
  • [50] Analysis of the APR1400 Benchmark Using High-Fidelity Pin-Wise Core Calculation Codes
    Yu, Hwanyeal
    Hong, Hyunsik
    Yoon, Jooil
    ENERGIES, 2024, 17 (14)
12345