Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Evaluation of Radiation Effect on Damage to Nuclear Fuel of Spent Fuel Transport CASK due to Sabotage Attack

사보타주 공격으로 인한 사용후핵연료 운반용기 격납 실패시 핵연료 손상에 따른 방사선 영향 평가

  • 박기호 (세종대학교 원자력공학과) ;
  • 김종성 (세종대학교 원자력공학과) ;
  • 차건일 (세종대학교 원자력공학과) ;
  • 박창제 (세종대학교 원자력공학과)
  • Received : 2022.11.14
  • Accepted : 2022.12.22
  • Published : 2022.12.30
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Abstract

The purpose of this study is to evaluate the radiation effect on damage when the external shield of the spent nuclear fuel transport cask is damaged due to impact as the cause of an unexpected accident. The neutron and gamma-ray intensities and spectra are calculated using the ORIGEN-Arp module in the SCALE 6.2.4 code package(1) and then using MCNP6.2(2) code calculate the dose rate. In order to evaluate the radiation dose according to the size of damage caused by external impact, various sized holes of 0.3~13.7% are assumed in the outer shield of the cask to evaluate the sensitivity to the dose. In the case of radiation source leakage, damage to the nuclear fuel assembly is assumed to be up to 6% based on overseas test cases. When only the outer shield is damaged, the maximum surface dose is calculated as 3.12E+03 mSv/hr. However, if the radiation source is leaked due to damage to the nuclear fuel assembly, it becomes 7.00E+05 mSv/hr which is about 200 times greater than the former case.

Keywords

Acknowledgement

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다(No. 2106064).

References

  1. SCALE : A Comprehensive Modeling and Simulation Suit for Nuclear Safety Analysis and Design, ORNL/TM-2005/39, Version 6.1, June 2011, Available from Radiation Safety Information Computational Center at Oak Ridge Natl. Lab., CCC-785.
  2. MCNP : MCNP6 USER's MANUAL, Version 1.0, May 2013, Manual Rev. 0
  3. Chung, S. H., Choi, B. I., Yang, K. H., and Lee, D. K., 2005, "On-Site Transport and Storage of Spent Nuclear Fuel at Kori NPP by KN-12 Transport Cask", J. of Korea Radioactive Waste Society, Vol. 4, pp. 51-58.
  4. KOREA NUCLEAR POWER TIMES, BACK, I. W., 2014,
  5. Bang, K. S, Yu, S. H., Lee, J. C., Seo, K. S and Choi W. S., 2018, "Theraml Test of KORAD-21 Cask", J. of Korea Radioactive Waste Society, pp. 87-88.
  6. Chung. S. W., Kim, K. Y and Kim, Y. D., 2016, "KN-18 Spent Nuclear Fuel Transport Cask", Proceedings of the 18th International Symposium on the Packaging and Transportation of Radioactive Materials PATRAM.
  7. Dho, H. S., Kim, T. M and Cho, C. H., 2016, "The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask", Korea Radioactive Waste Agency, Vol. 14, pp. 411-422. https://doi.org/10.7733/jnfcwt.2016.14.4.411
  8. RJ McConn Jr, CJ Gesh, RT Pagh, RA Rucker and RG William III, 2011, " Compendium of Material Composiion Data for Radiation Transport Modeling", Homeland Security, Pacific Northwest National Laboratory, PNNL-15870.
  9. M. Hanifehzadeh, B. Gencturk, and R. Mousavi, 2018, "A numerical study of spent nuclear fuel dry storage systems under extreme impact loading," Engineering Structures, Vol. 161, pp. 68-81.
  10. K, Shirai, K. Namba, and T. Saegusa, 2009, "Safety analysis of dual purpose metal cask subjectedto impulsive loads due to aircraft engine crash," J. of Power Energy Systems, Vol. 3(1), pp. 72-82. https://doi.org/10.1299/jpes.3.72
  11. Lee, S. H., Choi, W. S and Seo, K. S., 2016, "Safety assessment of a metal cask under aircraft engine crash," Nuclear Engineering and Technology, Vol. 48(2), pp. 505-517. https://doi.org/10.1016/j.net.2015.11.002
  12. ICRP PUBLICATION 21, 1971, "Data for Protection Against Ionizing from External Source Supplement to ICRP Publication 15".
  13. Nuclear Safety Commission Notice No. 2021-2, "Regulations on Packaging and Transport of Radioactive Materials, etc.".
  14. US.NRC, 1982, "Final Report on Shipping-Cask Sabotage Source Term Investigation", NUREG/CR-2472.
  15. Nuclear Safety Commission Notification No. 2019-10, Article 14 (Restriction of Dose in Emergency Radiation Work).