Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Data Analysis of International Joint Road and Sea Transportation Tests Under Normal Conditions of Transport

국제공동 육해상 정상운반시험의 데이터 분석

  • Received : 2020.04.29
  • Accepted : 2020.08.12
  • Published : 2020.08.30
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Abstract

In 2017, multimodal transportation tests for evaluating road, sea, and rail transport were performed by research institutes in the US, Spain, and the Republic of Korea. In this study, acceleration and strain data determined through road and sea tests were analyzed. It was investigated whether the load generated for each transport mode was amplified or attenuated according to the load transfer path. From the results, it was confirmed that the load transfer characteristics differed according to the transportation mode and loading path. The effects of strain determined through each test on the structural integrity of the spent nuclear fuel were also investigated. It was found that the magnitude of the measured strain had a negligible effect on the structural integrity of the spent nuclear fuel, considering its fatigue strength. The results for the acceleration and strain data analyses obtained in this study will be useful for scheduled domestic transportation tests under normal transport conditions.

2017년 미국 DOE 주도하에 수행된 국제공동 복합모드운반시험 중 도로트럭운반시험, 연안항해시험, 대서양항해시험에서 측정된 가속도 및 변형률 데이터를 분석하였다. 먼저 각 운반모드 별로 발생한 하중이 전달경로에 따라 하중이 증폭되는지 감쇄되는지가 조사되었다. 그 결과 운반모드 및 하중경로 내 어떤 부분이냐에 따라 발생한 하중이 모의핵연료집합체에 전달되는 특성이 다름을 확인하였다. 그리고 변형률 데이터를 분석하여 육상 및 해상운반동안 발생한 변형률이 사용후핵연료에 건전성에 미치는 영향을 파악하였다. 그 결과 측정된 변형률은 사용후핵연료의 건전성에는 영향을 미치지 못하는 정도로 작은 크기임을 확인하였다. 본 연구에서 분석된 가속도와 피로평가 결과는 예정된 국내 정상운반시험조건에서의 운반시험에 유용한 기초자료로 활용될 것이다.

Keywords

References

  1. Nuclear Safety and Security Commission, Regulation on the Delivery of Spent Nuclear Fuel, NSSC Notice No. 2017-64 (2017).
  2. U.S. Nuclear Regulatory Commission, Packaging and Transportation of Radioactive Material, Title 10, Code of Federal Regulation, Part 71, Washington, D.C. (1999).
  3. C.F. Magnuson, Shock and Vibration Environments for a Large Shipping Container during Truck Transport (Part II), Sandia National Laboratories Report, NUREG/ CR-0128, SAND78-0337 (1978).
  4. P. McConnell, Fuel-Assembly Shaker Test Plan-Tests for Determining Loads on Used Nuclear Fuel under Normal Conditions of Transport, U.S. Department of Energy Used Fuel Disposition Campaign, FCRDUFD- 2012-000341 (2012).
  5. P. McConnell, G. Flores, R. Wauneka, G. Koenig, D. Ammerman, J. Bignell, S. Saltzstein, and K. Sorenson, Fuel Assembly Shaker Test for determining Loads on a PWR Assembly under Surrogate Normal Conditions of Truck Transport, U.S. Department of Energy Fuel Cycle Research and Development, SAND2013-5210P Rev. 0.1, FCRD-UFD-2013-000190 (2013).
  6. P. McConnell, R. Wauneka, S. Saltzstein, and K. Sorenson, Normal Conditions of Transport Truck Test of a Surrogate Fuel Assembly, U.S. Department of Energy Fuel Cycle Research and Development, U.S. Department of Energy Used Fuel Disposition Campaign, FCRD-UFD-2014-000066 (2014).
  7. J.H. Lim, S.S. Cho, and W.S. Choi, "International Research Status on Spent Nuclear Fuel Structural Integrity Tests Considering Vibration and Shock Loads under Normal Conditions of Transport", J. Nucl. Fuel Cycle Waste Technol., 17(2), 167-181 (2019). https://doi.org/10.7733/jnfcwt.2019.17.2.167
  8. P. McConnell, S. Ross, C. Gray, W. Uncapher, M. Arviso, R. Garmendia, I. Pérez, A. Palacio, G. Calleja, D. Garrido, A. Casas, L. García, W. Chilton, D. Ammerman, J. Walz, S. Gershon, S. Saltzstein, K. Sorenson, N. Klymyshyn, B. Hanson, R. Peña, and R. Walker, Rail-Cask Tests: Normal-Conditions of-Transport Tests of Surrogate PWR Fuel Assemblies in an ENSA ENUN 32P Cask, SFWD-SFWST-2017-000004, January (2018).
  9. International Atomic Energy Agency, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Edition), IAEA SAFETY STANDARDS SERIES No. SSG-26 (2014).
  10. S.S. Cho, K.S. Seo, W.S. Choi, and J.H. Lim, Fatigue Analysis Methodology of Spent Nuclear Fuel Cladding due to Vibration and Shock Loadings under Normal Condition of Transport, Nuclear Safety Technology Analysis Report (2010).
  11. H.S. Kang, K.N. Song, H.K. Kim, and K.H. Yoon, "Modal Analysis of a PWR Fuel Rod Supported by the Newly Designed spacer grids", Transactions, SMiRT 16, Washington, D.C. (2001).
  12. L. Davis and J. Bunker, "Suspension Testing of 3 Heavy Vehicles - Methodology and Preliminary Frequency Analysis", Technical Report, Queensland University of Technology and Queensland Department of Main Roads (2008).
  13. W.J. O'Donnell and B.F. Langer, "Fatigue Design Basis for Zircaloy Components", Nucl. Sci. Eng., 20(1), 1-12 (1964). https://doi.org/10.13182/NSE64-A19269
  14. MATLAB User's Manual (2019).