Published October 2013 | Version v1
Miscellaneous

Development of Finite Element Model for the Static Buckling Behavior of the Spacer Grid

  • 1. Kepco Nuclear Fuel, Daejeon (Korea, Republic of)

Description

In this study, finite element model was proposed to evaluate the buckling characteristics and structural behavior of partial spacer grids. A two-dimensional model was developed to simplify a real spacer gird model and save analysis time. And it was validated for comparison with experimental tests. A non-linear analysis method was introduced to perform realistic simulation. Later, the buckling analysis of the full size grid will be performed based on the analysis results of partial spacer grids. A study was conducted to develop the simplified model of a spacer grid and provide a prediction of buckling behavior. The FE analysis results are quite similar to the experimental tests. · The deformed geometry of FE model after compression is consistent and very similar to that of real situation, and the non-linear analysis method used in this model can simulate buckling and post-buckling behavior well. · The buckling strength obtained by FEM shows a very good agreement with the physical tests

Part of:
Proceedings of the KNS Fall meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS Fall meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2013 Fall meeting of the KNS
Dates
23-25 Oct 2013
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45082199
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BUCKLING; FINITE ELEMENT METHOD; FORECASTING; FUEL ASSEMBLIES; FUEL RODS; GRIDS; LOSS OF COOLANT; SPACERS; VALIDATION
Descriptors DEC
ACCIDENTS; CALCULATION METHODS; ELECTRODES; FUEL ELEMENTS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS; TESTING

Optional Information

Notes
5 refs, 5 figs