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Radiological analysis of transport and storage container for very low-level liquid radioactive waste

  • Shin, Seung Hun (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Choi, Woo Nyun (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Yoon, Seungbin (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Un Jang (ORION EnC Co., Ltd.) ;
  • Park, Hye Min (ORION EnC Co., Ltd.) ;
  • Park, Seong Hee (ORION EnC Co., Ltd.) ;
  • Kim, Youn Jun (ORION EnC Co., Ltd.) ;
  • Kim, Hee Reyoung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
  • Received : 2021.01.20
  • Accepted : 2021.06.13
  • Published : 2021.12.25

Abstract

As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is designed by considering related regulations. The design was constructed based on the existing container design, which easily transports and stores liquid waste. The radiation shielding calculation was performed according to the composition change of barium sulfate (BaSO4) using the Monte Carlo N-Particle (MCNP) code. High-density polyethylene (HDPE) without mixing the additional BaSO4, represented the maximum dose of 1.03 mSv/hr (<2 mSv/hr) and 0.048 mSv/hr (<0.1 mSv/hr) at the surface of the inner container and at 2 m away from the surface, respectively, for a 10 Bq/g of 60Co source. It was confirmed that the dose from the inner container with the VLLW content satisfied the domestic dose standard both on the surface of the container and 2 m from the surface. Although it satisfies the dose standard without adding BaSO4, a shielding material, the inner container was designed with BaSO4 added to increase radiation safety.

Keywords

Acknowledgement

This work was supported by the Ulsan City Research Fund (1.200068.01) of UNIST (Ulsan National Institute of Science & Technology). This work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korean government (MSIP: Ministry of Science, ICT and Future Planning) NRF-2016M2B2B1945082.

References

  1. K.M. Lee, J.H. Kim, S.H. Kang, Preliminary evaluation of decommissioning wastes for the first commercial nuclear power reactor in South Korea, Int. J. Nucl. Quantum Eng. 11 (8) (2018) 615-621.
  2. J.H. Lee, Y.H. Hwang, B.G. Lee, C.W. Kim, Waste characterization and treatment methodology for decommissioning of Kori 1 Unit, in: International Nuclear Fuel Cycle Conference, Seoul, Korea, 2017.
  3. IAEA, Regulations for the Safe Transport of Radioactive Material, 2018. IAEA Safety Standard Series No. SSR-6, Vienna.
  4. NSSC, Regulations on Package and Transport of Radioactive Material, Act No. 2019-7, 2019.
  5. S.C. Kim, K.R. Dong, W.K. Chung, Performance evaluation of a medical radiation shielding sheet with barium as an environment-friendly material, J. Kor. Phys. Soc. 60 (1) (2012) 165-170. https://doi.org/10.3938/jkps.60.165
  6. NSSC, Regulations on Radioactive Waste Classification and Self-Disposal Standard, 2020. Act No. 2020-6.
  7. T. Goorley, et al., Initial MCNP 6 release overview, Nucl. Technol. 180 (3) (2012) 298-315. https://doi.org/10.13182/NT11-135
  8. D.A. Brown, et al., ENDF/B-VIII.0: the 8th Major release of the nuclear reaction data library with CIELO-project cross sections, New Standards and Thermal Scattering Data, Nucl. Data Sheets 148 (2018) 1-142.