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Impact Analysis of a Dipper-Type and Multi Spring-Type Fuel Rod Support Grid Assemblies in PWR

[+] Author Affiliations
K. N. Song, K. H. Yoon

Korea Atomic Energy Research Institute, Taejon, Korea

K. J. Park, G. J. Park, B. S. Kang

Hanyang University, Ansan, Korea

Paper No. ICONE10-22177, pp. 533-540; 8 pages
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 1
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3595-2 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME


A spacer grid is one of the main structural components in a fuel assembly of a Pressurized light Water Reactor (PWR). It supports fuel rods, guides cooling water, and maintains geometry from external impact loads. A simulation is performed for the strength of a spacer grid under impact load. The critical impact load that leads to plastic deformation is identified by a free-fall test. A finite element model is established for the nonlinear simulation of the test. The simulation model is tuned based on the free-fall test. The model considers the aspects of welding and the contacts between components. Nonlinear finite element analysis is carried out by a software system called LS/DYNA3D. The results are discussed from a design viewpoint.

Copyright © 2002 by ASME



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