Deformation Characteristics and Sealing Performance of Metallic O-rings for a Reactor Pressure Vessel

被引:23
作者
Shen, Mingxue [1 ]
Peng, Xudong [1 ]
Xie, Linjun [1 ]
Meng, Xiangkai [1 ]
Li, Xinggen [2 ]
机构
[1] Zhejiang Univ Technol, Minist Educ, Engn Res Ctr Proc Equipment & Its Remanufacture, 18 Chaowang Rd, Hangzhou 310032, Zhejiang, Peoples R China
[2] Ningbo Tiansheng Sealing Packing Co Ltd, 418 Gaoke Ave, Ningbo 315302, Zhejiang, Peoples R China
基金
美国国家科学基金会;
关键词
Deformation Characteristic; Inconel; 718; Metallic O-Ring; Reactor Pressure Vessel; Sealing Performance; C-RINGS;
D O I
10.1016/j.net.2015.11.009
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
This paper provides a reference to determine the seal performance of metallic O-rings for a reactor pressure vessel (RPV). A nonlinear elastic-plastic model of an O-ring was constructed by the finite element method to analyze its intrinsic properties. It is also validated by experiments on scaled samples. The effects of the compression ratio, the geometrical parameters of the O-ring, and the structure parameters of the groove on the flange are discussed in detail. The results showed that the numerical analysis of the O-ring agrees well with the experimental data, the compression ratio has an important role in the distribution and magnitude of contact stress, and a suitable gap between the side wall and groove can improve the sealing capability of the O-ring. After the optimization of the sealing structure, some key parameters of the O-ring (i.e., compression ratio, cross-section diameter, wall thickness, sidewall gap) have been recommended for application in megakilowatt class nuclear power plants. Furthermore, air tightness and thermal cycling tests were performed to verify the rationality of the finite element method and to reliably evaluate the sealing performance of a RPV. Copyright (C) 2015, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society.
引用
收藏
页码:533 / 544
页数:12
相关论文
共 18 条
[1]   PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling-60 years foreseen plant lifetime [J].
Al Mazouzi, A. ;
Alamo, A. ;
Lidbury, D. ;
Moinereau, D. ;
Van Dyck, S. .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) :3403-3415
[2]  
Cai RL., 2013, FLUID SEALING TECHNO
[3]   Variational formulations for the plane strain elastic-plastic problem for materials governed by the von Mises criterion [J].
Capsoni, A ;
Corradi, L .
INTERNATIONAL JOURNAL OF PLASTICITY, 1996, 12 (04) :547-560
[4]   Sustainability of the Chinese nuclear expansion: Natural uranium resources availability, Pu cycle, fuel utilization efficiency and spent fuel management [J].
Fiori, F. ;
Zhou, Z. .
ANNALS OF NUCLEAR ENERGY, 2015, 83 :246-257
[5]   Characterising and reducing seizure wear of inconel and incoloy superalloys in a sliding contact [J].
Houghton, A. ;
Lewis, R. ;
Olofsson, U. ;
Sundh, J. .
WEAR, 2011, 271 (9-10) :1671-1680
[6]   A study on the sealing performance of metallic C-rings in reactor pressure vessel [J].
Jia, Xiaohong ;
Chen, Huaming ;
Li, Xinggen ;
Wang, Yuming ;
Wang, Longke .
NUCLEAR ENGINEERING AND DESIGN, 2014, 278 :64-70
[7]   A new design concept of metal O-ring seal for long-term performance [J].
Kim, G. H. ;
Lee, Y. S. ;
Yang, H. L. .
VACUUM, 2016, 123 :54-61
[8]  
Kobayashi T., 1999, ANAL BOLTED JOINTS 1
[9]   FEASIBILITY OF AN INTEGRATED STEAM GENERATOR SYSTEM IN A SODIUM-COOLED FAST REACTOR SUBJECTED TO ELEVATED TEMPERATURE SERVICES [J].
Koo, Gyeong-Hoi ;
Lee, Jae-Han .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (08) :1115-1126
[10]   Three-dimensional transient sealing analysis of the bolted flange connections of reactor pressure vessel [J].
Lin, Tengjiao ;
Li, Runfang ;
Long, H. ;
Ou, H. .
NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (24) :2599-2607