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원자력이용시설 해체 후 부지 재이용 안전성평가 시 부지 특성인자 민감도 분석

Site Specific Parameters Sensitivity Analysis for Site Reuse after Decommissioning Nuclear Facilities

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초록

In Korea, in order to complete the decommissioning of the nuclear facility, radiationdose due to residual radioactivity in the site or remaining buildings following (dose based)decommissioning satisfy site reuse criteria. When safety assessment of site reuse after decommissioning,site specific parameter should be used for reliable assessment. In this study, the sensitivityanalysis of the distribution coefficient, transfer factors, and bioaccumulation factor, which are themajor site specific parameter for the safety assessment were performed. The nuclides were selectedbased on decommissioning cases of overseas NPP, and 12 of the total 13 nuclides were selected asthe target nuclides. Resident farmer scenario was applied as an exposure scenario. Distributioncoefficient, transfer factors, and bioaccumulation factor were selected for sensitivity analysis. NDD(Normalized Dose Difference) was used as a sensitivity analysis method. For the application ofNDD, the statistical distribution presented in NUREG/CR-6697 was used. The 5th percentile wasapplied as the low value, the mean value was applied as the base value, and the 95th percentile wasapplied as the high value. As a result of sensitivity analysis, it was found that the contaminatedlayer distribution coefficient was sensitive to 99Tc and 90Sr. The distribution coefficients of theunsaturated and saturated layers were found to be insensitive to all nuclides. When the site has onesoil texture, the distribution coefficient was sensitive to 14C, 90Sr, 99Tc, and 241Am. In the case of planttransfer factor, it was sensitive to 63Ni, 90Sr, 99Tc, 238Pu, 241Am, and 241Pu. Meat transfer factor wassensitive to 55Fe, and milk transfer factor was sensitive to 63Ni. The bioaccumulation factor for fishwas insensitive to all nuclides. As a result of the sensitivity analysis, it was found that the degree ofsensitivity of the distribution coefficient and the transfer factor varies depending on the nuclide. Anddistribution coefficient and the transfer factor have a large influence on the change in the maximumdose overall. Therefore, in order to evaluate the safety of site reuse after decommissioning of nuclearfacilities, it is considered that reliable results can be derived only when the site-specific parametersare obtained and reflected in the evaluation.

Abstract

In Korea, in order to complete the decommissioning of the nuclear facility, radiationdose due to residual radioactivity in the site or remaining buildings following (dose based)decommissioning satisfy site reuse criteria. When safety assessment of site reuse after decommissioning,site specific parameter should be used for reliable assessment. In this study, the sensitivityanalysis of the distribution coefficient, transfer factors, and bioaccumulation factor, which are themajor site specific parameter for the safety assessment were performed. The nuclides were selectedbased on decommissioning cases of overseas NPP, and 12 of the total 13 nuclides were selected asthe target nuclides. Resident farmer scenario was applied as an exposure scenario. Distributioncoefficient, transfer factors, and bioaccumulation factor were selected for sensitivity analysis. NDD(Normalized Dose Difference) was used as a sensitivity analysis method. For the application ofNDD, the statistical distribution presented in NUREG/CR-6697 was used. The 5th percentile wasapplied as the low value, the mean value was applied as the base value, and the 95th percentile wasapplied as the high value. As a result of sensitivity analysis, it was found that the contaminatedlayer distribution coefficient was sensitive to 99Tc and 90Sr. The distribution coefficients of theunsaturated and saturated layers were found to be insensitive to all nuclides. When the site has onesoil texture, the distribution coefficient was sensitive to 14C, 90Sr, 99Tc, and 241Am. In the case of planttransfer factor, it was sensitive to 63Ni, 90Sr, 99Tc, 238Pu, 241Am, and 241Pu. Meat transfer factor wassensitive to 55Fe, and milk transfer factor was sensitive to 63Ni. The bioaccumulation factor for fishwas insensitive to all nuclides. As a result of the sensitivity analysis, it was found that the degree ofsensitivity of the distribution coefficient and the transfer factor varies depending on the nuclide. Anddistribution coefficient and the transfer factor have a large influence on the change in the maximumdose overall. Therefore, in order to evaluate the safety of site reuse after decommissioning of nuclearfacilities, it is considered that reliable results can be derived only when the site-specific parametersare obtained and reflected in the evaluation.

참고문헌 (22)

  1. 원자력안전위원회, "원자력이용시설 해체완료 후 부지 및 잔존건물의 재이용을 위한 기준", 원자력안전위원회고시 제2016-33호, ~ (2016)
  2. 원자력안전위원회, "원자력안전법. 법률 제17359호", ~ (2020)
  3. ANL, "Postremediation Dose Assessment for the Formal Alba Craft Laboratory Site", ANL, TM-55, pp.1996, ~
  4. ANL, "Radiological Dose Assessment for the Dismantlement and Decommissioning Option for the Heavy Water Components Test Reactor Facility at the Savannah River Site", ANL, TM-77, pp.1997, ~
  5. ANL, "User’s Manual for RESRAD Version 6", ANL, 2001
  6. ANL, "Derived Concentration Guideline Levels for Argonne National Laboratory’s Building 310 Area", ANL, TM, pp.11-4, 2011[DOI]
  7. 홍상범, "Application of MARSSIM for Final Status Survey of the Decommissioning Project", Journal of Nuclear Fuel Cycle and Waste Technology, 9(2), pp.107~111 (2011), 한국방사성폐기물학회
  8. Hong SB, "Practical application of the MARSSIM process to the site release of a Uranium Conversion Plant following decommissioning", Ann. Nucl. Energy, 65, pp.241~246 (2014)
  9. IAEA, "Release of Sites from Regulatory Control on Termination of Practices", IAEA Safety Guide No. WS-G-5.1, ~ (2006)
  10. IAEA, "Nuclear Power Reactors in the World", Reference Data Series No. 2, ~ (2020)
  11. The 2007 Recommendations of the international commission on radiological protection, "ICRP", ~, pp.ICRP Publication 103 (2007)
  12. Kamboj S, "Deterministic vs. probabilistic analyses to identify sensitive parameters in dose assessment using RESRAD", Health Phys, 88(5), pp.104~109 (2005)
  13. NRC, "Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes", NUREG, 2000
  14. NRC, "Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria", NUREG-1757, ~ (2002)
  15. Park SJ, "Comparative Analysis of Probabilistic Analysis and Deterministic Analysis by RESRAD Code", Energies, 13(8), pp.1983~1995 (2020)
  16. PG & E, "Humboldt Bay Power Plant, Unit 3, License Termination Plan, Revision 1", ~ (2014)
  17. 서형우, "Calculation of Preliminary Site-Specific DCGLs for Nuclear Power Plant Decommissioning Using Hybrid Scenarios", Nuclear Engineering and Technology, 51(4), pp.1098~1108 (2019), 한국원자력학회[DOI]
  18. Seo HW, "Scenario options to calculation of Derived Concentration Guideline Levels for a multi-unit decommissioning site", Ann. Nucl. Energy, 133, pp.347~358 (2019)
  19. 서형우, "Proposal for the list of potential radionuclides of interest during NPP site characterization or fi nal status surveys", Nuclear Engineering and Technology, 53(1), pp.234~243 (2021), 한국원자력학회[DOI]
  20. Sheppard MI, "Mobility and Plant Uptake of Inorganic 14C and 14C-labelled Pcb in Soils of High and Low Retention", Health Phys, 61(4), pp.481~492 (1991)
  21. SMUD, "Rancho Seco Nuclear Generating Station License Termination Plan, Revision 1", ~ (2008)
  22. Nuclear Plant Station License Termination Plan, "Yankee Atomic Electric Company", ~ (2004)

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