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Analysis of an Aircraft Impact on a Dry Storage Cask of Spent Nuclear Fuel

  • Edgar Hernández-Palafox
  • Juan Cruz-Castro
  • Yunuén López-Grijalba
  • Luis Héctor Hernández-Gómez
  • Guillermo Manuel Urriolagoitia-Calderón
  • Laura Guadalupe Carbajal-Figueroa
Chapter
  • 64 Downloads
Part of the Advanced Structured Materials book series (STRUCTMAT, volume 124)

Abstract

Nowadays, nuclear power plants can use a dry storage cask (DSC) for the spent nuclear fuel (NSF) on site. It is a reinforced concrete vessel, which has an internal stainless steel cylinder. Its main function is to provide a barrier against radiation, to cool down the spent fuel and to avoid nuclear fission through the internal metallic surface that contains the radioactive material. This vessel has been designed to withstand different conditions such as free fall, penetration, crushing and extreme temperatures. However, there is limited knowledge about the assessment of an aircraft impact on such vessels in the open literature. In this paper, the case of an oblique impact (45° impact angle with respect to the horizontal) of a light aircraft against a dry storage cask was considered. Its structural integrity was evaluated. The containers were considered to be located in an outdoor area. The evaluation was carried out with the commercial ANSYS® code.

Keywords

Spent fuel storage pool Independent spent fuel storage installations Aircraft impact Structural integrity Explicit dynamics analysis 

Nomenclature

CAD

Computational Assisted Design

CATIA

Computer-Aided Three-dimensional Interactive Application

DSC

Dry Storage Cask

EPRI

Electric Power Research Institute

FEA

Finite Element Analysis

FEM

Finite Element Method

ISFSI

Independent Spent Fuel Storage Installations

CSN

Nuclear Safety Council

NPP

Nuclear Power Plant

SFSP

Spent Fuel Storage Pool

SNF

Spent Nuclear Fuel

USNRC

United States Nuclear Regulatory Commission

\(\delta (t)\)

Green function

[C]

Damping matrix

\({F_1}(t)\)

Time-dependent load including impact/explosion

[K]

Stiffness matrix

[M]

Structural mass matrix

MTU

Metric Ton of Uranium

\(\left\{ {R(t)} \right\}\)

Residual time-dependent load vector

\(\left\{ {\dot x} \right\}\)

Structural velocity matrix

\(\left\{ {\ddot x} \right\}\)

Structural acceleration matrix

Notes

Acknowledgements

The authors kindly acknowledge the grant for the development of the Project 211704. It was awarded by the National Council of Science and Technology (CONACyT).

References

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Copyright information

© Springer Nature Switzerland AG 2020

Authors and Affiliations

  • Edgar Hernández-Palafox
    • 1
  • Juan Cruz-Castro
    • 1
  • Yunuén López-Grijalba
    • 2
  • Luis Héctor Hernández-Gómez
    • 1
  • Guillermo Manuel Urriolagoitia-Calderón
    • 1
  • Laura Guadalupe Carbajal-Figueroa
    • 1
  1. 1.Instituto Politécnico Nacional, Sección de Estudios de Posgrado e Investigación, Escuela Superior de Ingeniería Mecánica y Eléctrica, Unidad Zacatenco, “Unidad Profesional Adolfo López Mateos”Ciudad de MéxicoMexico
  2. 2.Instituto Politécnico Nacional. Unidad Profesional Interdisciplinaria de IngenieríaSan Agustín Tlaxiaca, HidalgoMexico

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