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

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Evaluation of Exposure Dose and Working Hours for Near Surface Disposal Facility

  • Received : 2022.08.09
  • Accepted : 2022.10.13
  • Published : 2022.12.30
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Abstract

Decommissioning of nuclear power plants generates a large amount of radioactive waste in a short period. Moreover, Radioactive waste has various forms including a large volumes of metal, concrete, and solid waste. The disposal of decommissioning waste using 200 L drums is inefficient in terms of economics, work efficiency, and radiation safety. Therefore, The Korea Radioactive Waste Agency is developing large containers for the packaging, transportation, and disposal of decommissioning waste. Assessing disposability considering the characteristics of the radioactive waste and facility, convenience of operation, and safety of workers is necessary. In this study, the exposure dose rate of workers during the disposal of new containers was evaluated using Monte Carlo N-Particle Transport code. Six normal and four abnormal scenarios were derived for the assessment of the dose rate in a near surface disposal facility operation. The results showed that the calculated dose rates in all normal scenarios were lower than the direct exposure dose limitation of workers in the safety analysis report. In abnormal scenarios, the work hours with dose rates below 20 mSv·y-1 were calculated. The results of this study will be useful in establishing the optimal radiation work conditions.

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Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP Project No. 2021151010040) and the Ministry of Trade, Industry & Energy (MOTIE) of the Republic of Korea.

References

  1. Korea Radioactive Waste Agency. Annual Report of Development of Waste Package, Transportation and Disposal Containers for Decommissioning Wastes of Nuclear Power Plant, KORAD Report (2020).
  2. Korea Radioactive Waste Agency, The Operating Procedure of Low and Intermediate Level Radioactive Waste Disposal Facilities - Operating of As Low As Reasonably Achievable (ALARA), No. LILW-Operation-Radiation-075 (2021).
  3. Korea Radioactive Waste Agency, The Operating Procedure of Low and Intermediate Level Radioactive Waste Disposal Facilities - Management of Radiation Exposure Dose, Notice No. LILW-Operation-Radiation-041 (2022).
  4. R.A. Kim, H.S. Dho, T.M. Kim, and C.H. Cho, "The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility", J. Nucl. Fuel Cycle Waste Technol., 18(2_spc), 317-325 (2020). https://doi.org/10.7733/jnfcwt.2020.18.2(E).317
  5. International Commission on Radiological Protection, ICRP Publication 74: Conversion Coefficients for Use in Radiological Protection Against External Radiation, 1st ed., ICRP, London (1996).
  6. Los Alamos National Laboratory, MCNP User's Manual - Code Version 6.2, LA-UR-17-29981 (2017).
  7. Korea Radioactive Waste Agency. Report on Performance Evaluation of Internal Grouting of Near Surface Disposal Facility, KORAD Report (2019).
  8. Korea Radioactive Waste Agency. Safety Analysis Report for the Second Phase Near Surface Low and Intermediate Level Waste Disposal Facility, KORAD Report (2016).