Structural assessments of plate type support system for APR1400 reactor Anh Tung Nguyen, Ihn Namgung

被引:4
|
作者
Anh Tung Nguyen [1 ]
Namgung, Ihn [1 ]
机构
[1] KEPCO Int Nucl Grad Sch, 658-91 Haemaji Ro, Ulsan 689882, South Korea
关键词
Non-linear thermal stress analysis; Buckling analysis; Nuclear reactor support; ASME code stress evaluation;
D O I
10.1016/j.nucengdes.2017.01.026
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 investigates an alternative form of support structure for the reactor vessel of the APR 1400. The current reactor vessel adopts a four-column support arrangement locating on the cold legs of the vessel. Although having been successfully designed, the tall column structure challenges in seismic events. In addition, for the mitigation of severe accident consequences, the columns inhibit ex-vessel coolant flow, hence the elimination of the support columns proposes extra safety advantages. A plate-type support was proposed and evaluated for the adequacy of meeting the structural stiffness by Finite Element Analysis (FEA) approach. ASME Boiler and Pressure Vessel Code was used to verify the design. The results, which cover thermal and static structural analysis, show stresses are within allowable limits in accordance with the design code. Even the heat conduction area is increased for the plate-type of support system, the results showed that the thermal stresses are within allowable limits. A comparison of natural frequencies and mode shapes for column support and plate-type support were presented as well which showed higher fundamental frequencies for the plate-type support system resulting in greater rigidity of the support system. From the outcome of this research, the plate-type support is proven to be an alternative to current APR column type support design. (C) 2017 Elsevier B.V. All rights reserved.
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页码:256 / 270
页数:15
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