Composites Research

  • 제28권2호
  • /
  • Pages.58-64
  • /
  • 2015
  • /
  • 2288-2103(pISSN)
  • /
  • 2288-2111(eISSN)
한국복합재료학회 (The Korean Society for Composite Materials)
권호 표지
DOI QR코드

DOI QR Code

사용후 핵연료 수송용기 샌드위치 복합재 충격완충체의 유효등가 유한요소 모델 제시

Effective Equivalent Finite Element Model for Impact Limiter of Nuclear Spent Fuel Shipping Cask made of Sandwich Composites Panels

  • Kang, Seung-Gu (Graduate School of Mechanical Engineering, Hanbat National University) ;
  • Im, Jae-Moon (Graduate School of Mechanical Engineering, Hanbat National University) ;
  • Shin, Kwang-Bok (Department of Mechanical Engineering, Hanbat National University) ;
  • Choi, Woo-Suk (Division of Fuel Cycle System, Korea Atomic Energy Research Institute)
  • 투고 : 2015.02.10
  • 심사 : 2015.04.28
  • 발행 : 2015.04.30
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

본 논문에서는 샌드위치 복합재 패널로 제작되는 사용후 핵연료 수송용기 충격완충체의 유효등가 유한 요소모델을 제시하는데 목적을 둔다. 샌드위치 복합재 패널은 금속재 면재와 각각 우레탄 폼, 발사목 그리고 레드우드 심재로 구성되었다. 충격완충체의 유효등가 유한요소 모델은 샌드위치 복합재 패널의 저속충격 시험과 해석결과와의 비교를 통해 제시되었으며, LS-DYNA 3D를 사용한 동적 외연 유한요소해석에 의해 수행되었다. 시험과 해석 결과, 충격완충체 샌드위치 패널의 유한요소 모델은 적층쉘 요소의 면재와 솔리드요소의 심재를 사용한 기존의 혼합모델링 기법에 비해 면재와 심재 모두 솔리드 요소를 적용하는 방법이 더 정확한 결과를 나타냄을 확인하였다. 이때 발사목과 레드우드 심재는 요소제거 기능을 갖는 솔리드 요소로 모델링 되는 것이 추천되어진다.

The purpose of this paper is to suggest the effective equivalent finite element model for the impact limiter of a nuclear spent fuel shipping cask made of sandwich composite panels. The sandwich composite panels were composed of a metallic facesheet and a core material made of urethane foam, balsa wood and red wood, respectively. The effective equivalent finite element model for the impact limiter was proposed by comparing the results of low-velocity impact test of sandwich panels. An explicit finite element analysis based on LS-DYNA 3D was done in this study. The results showed that the solid elements were recommended to model the facesheet and core of sandwich panels for impact limiter compared to combination modeling method, in which the layered shell element for facesheet and solid element for core material are used. In particular, the solid element for balsa and red wood core materials should be modeled by the element elimination approach.

키워드

참고문헌

  1. Kang, S.G., Shin, K.B., Goo, J.S., and Choi, W.S., "Evaluation of Impact Characteristics of Absorber Materials for Spent Fuel Shipping Cask using Numerical Analysis", Proceeding of the Korean Society for Precision Engineering, Gwangju, Korea, Oct. 2012, pp. 789-790.
  2. Goo, J.S., Shin, K.B., and Choi, W.S., "Evaluation of Mechanical Properties and Low-Velocity Impact Characteristics of Balsa-Wood and Urethane-Foam Applied to Impact Limiter of Nuclear Spent Fuel Shipping Case", Transactions of the Korean Society of Mechanical Engineers A, Vol. 36, No. 11, 2012, pp. 1345-1352. https://doi.org/10.3795/KSME-A.2012.36.11.1345
  3. IAEA, 1985, "Regulations for the Safe Transport of Radioactive Materials", IAEA Safety Series, No. 6.
  4. Chung, S.H., and Lee, Y.S., "A Study on the Side Drop Impact of a Nuclear Spent Fuel Shipping Cask", Transactions of the Korean Society of Mechanical Engineers A, Vol. 21, No. 3, 1997, pp.457-469. https://doi.org/10.22634/KSME-A.1997.21.3.457
  5. Lee, Y.S., and Kim, Y.J., "A Study on the Dynamic Behaviors of a Shipping Container Under Drop Impact Loading", Transactions of the Korean Society of Mechanical Engineers, Vol. 18, No. 11, 1994, pp. 2805-2816. https://doi.org/10.22634/KSME.1994.18.11.2805
  6. Ku, J.H., Seo, K.S., Min, D.K., and Kim, Y.J., "Effect of the Weldement Failure of Cask Impact Limiter on the Impact Absorbing Behavior," Transactions of the Korean Society of Mechanical Engineers A, Vol. 22, No. 12, 1998, pp. 2286-2295.
  7. Kim, K.S., Kim, J.S., Choi, K.S., Shin, T.M., and Yun, H.D., "Dynamic Impact Characteristics of KN-18 Transport Cask - Part 2 : Sensitivity Analysis of Modeling and Design Parameters," Annals of Nuclear Energy, Vol. 37, 2010, pp. 560-571. https://doi.org/10.1016/j.anucene.2009.12.024
  8. Aquaro, D., Zaccari, N., Di Prinzio, M., and Forasassi, G., "Numerical and Experimental Analysis of the Impact of a Nuclear Spent Fuel Cask," Nuclear Engineering and Design, Vol. 240, 2010, pp. 706-712. https://doi.org/10.1016/j.nucengdes.2009.12.018
  9. Ku, J.H., Seo, K.S., Park, S.W., and Kim, Y.J., "Beneficial Influence of the Weldment Rupture of Cask Impact Limiter Case on the Impact Absorbing Behavior," Nuclear Engineering and Design, Vol. 196, 2000, pp. 263-279. https://doi.org/10.1016/S0029-5493(99)00305-2
  10. ASTM International, "Standard Test Method for Tensile and Tensile Adhesion Properties of Rigid Cellular Plastics," 2003, ASTM D1623.
  11. ASTM International, "Standard Test Method for Flexible Cellular Materials-Slab, Bonded and Molded Urethane Foams,"2003, ASTM D3574.
  12. ASTM International, "Standard Test Method for Flatwise Compressive Properties of Sandwich Cores," 2003, ASTM C365.
  13. ASTM International, "Standard Test Method for Shear Properties of Sandwich Core Materials," 2003, ASTM C273.
  14. Jang, H.J., Shin, K.B., Ko, H.Y., and Ko, T.H., "A Study on the Standardized Finite Element Models for Carbody Structures of Railway Vehicle Made of Sandwich Composites," Journal of the Korean Society for Railway, Vol. 13, No. 4, 2010, pp. 382-388.
  15. Goo, J.S., "A Study on Low-velocity Impact Characteristics of Impact Limiter Materials applied to Nuclear Spent Fuel Shipping Cask," Master's Thesis, Hanbat National University, Korea, 2013.