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

Korean Radioactive Waste Society (한국방사성폐기물학회)
권호 표지
DOI QR코드

DOI QR Code

Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code

  • Received : 2020.10.27
  • Accepted : 2020.12.18
  • Published : 2021.03.30
Download PDF
⟨ Previous Next ⟩

Abstract

Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 ㎡ with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials' density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10-4 mSv·yr-1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

Keywords

References

  1. M. Song, C.L. Kim, and D.S. Kessel, "Consideration of Spent Fuel Pool Island as an Interim Management Option of Spent Nuclear Fuel for Kori Unit 3 & 4 During Decommissioning of Kori Site", Ener. Stra. Rev., 21 163-171 (2018). https://doi.org/10.1016/j.esr.2018.06.007
  2. J. Byon, S. Park, and S. Ahn, "Radionuclide-Specific Exposure Pathway Analysis of Kori Unit 1 Containment Building Surface", J. Nucl. Fuel Cycle Waste Technol., 18(3), 347-354 (2020). https://doi.org/10.7733/jnfcwt.2020.18.3.347
  3. F. Aspe, R. Idoeta, G. Auge, and M. Herranz, "Classification and Categorization of the Constrained Environments in Nuclear/Radiological Installations Under Decommissioning and Dismantling Processes", Prog. Nucl. Energy, 124, 103347 (2020). https://doi.org/10.1016/j.pnucene.2020.103347
  4. B. Setiawan, S. Prihastuti, and S.S. Moersidik, "137Cs Radiological Risk Estimation of NSD Facility at Karawang Site by Using RESRAD Onsite Application: Effect of Cover Thickness", J. Phys. A, 962(1), 012053 (2018).
  5. J.J. Cheng and C. Yu, "Using the RESRAD Computer Code to Evaluate Human Health Risks from Radionuclides and Hazardous Chemicals", J. Hazard. Mater., 35(3), 353-367 (1993). https://doi.org/10.1016/0304-3894(93)85042-D
  6. S.J. Park, J. Byon, D.H. Ban, S. Lee, W. Sohn, and S. Ahn, "Derivation of Preliminary Derived Concentration Guideline Level (DCGL) by Reuse Scenario for Kori Unit 1 Using RESRAD-BUILD", Nucl. Eng. Technol., 52(6), 1231-1242 (2020). https://doi.org/10.1016/j.net.2019.11.032
  7. E.F. Salem, M. Abdelati, and K.M.E Kourghly, "Assessment of Potential Risk Due to Accidental Melting of Scrap Metal Containing Depleted Uranium Using a Computational Method", Am. J. Environ. Sci. Eng., 3(3), 60-65 (2019). https://doi.org/10.11648/j.ajese.20190303.13
  8. S.H. Lee. A Study on Improvement Plan for Nuclear Regulatory Administration System, Korea Institute of Nuclear Safety Report, KINS/GR-119 (1996).
  9. H.G. Kim, S.W. Han, S.R. Park, and B.J. Kim, "Safety Assessment on the Incineration Disposal of Regulation Exempt Waste by RESRAD Code", J. Radiol. Sci. Tech., 41(1), 67-73 (2018). https://doi.org/10.17946/JRST.2018.41.1.67
  10. M.J. Azlina, B. Ismail, M.S. Yasir, S.H. Sakuma, and M.K. Khairuddin, "Radiological Impact Assessment of Radioactive Minerals of Amang and Ilmenite on Future Landuse Using RESRAD Computer Code", Appl. Radiat. Isotopes, 58(3), 413-419 (2003). https://doi.org/10.1016/S0969-8043(02)00347-0
  11. N.J. AbuAlRoos, N.A.B. Amin, and R. Zainon, "Conventional and New Lead-Free Radiation Shielding Materials for Radiation Protection in Nuclear Medicine: A Review", Radiat. Phys. Chem., 165, 108439 (2019). https://doi.org/10.1016/j.radphyschem.2019.108439
  12. J. Zeb, W. Arshed, and S.S. Ahmad. Radiation Dose Reduction by Water Shield, Pakistan Institute of Nuclear Science & Technology Technical Report, 1-29, PINSTECH-199 (2007).