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A study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1

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초록

In the calculation of DCGLs using RESRAD code, the selection of input parameter values is paramount, which is basically possible when specific measures for selecting reuse scenarios and probabilistic evaluation methods are established. When referring to the impact of the age group considered in the environmental impact assessment among the existing operations of the plant, it may also need to be applied in the decommissioning project, and there will be considerations along with site reuse scenarios and probabilistic evaluations. Therefore, the main purpose of this study is to distinguish the types of exposure affected by residual radioactivity contamination during the process of deriving DCGL to be used in the final site release stage of NPPs and to evaluate them by reasonably assigning age group parameter values. In addition, the case of entering a single value for parameter values by age group and the case of entering probabilistic distributions were compared and analyzed.

Abstract

In the calculation of DCGLs using RESRAD code, the selection of input parameter values is paramount, which is basically possible when specific measures for selecting reuse scenarios and probabilistic evaluation methods are established. When referring to the impact of the age group considered in the environmental impact assessment among the existing operations of the plant, it may also need to be applied in the decommissioning project, and there will be considerations along with site reuse scenarios and probabilistic evaluations. Therefore, the main purpose of this study is to distinguish the types of exposure affected by residual radioactivity contamination during the process of deriving DCGL to be used in the final site release stage of NPPs and to evaluate them by reasonably assigning age group parameter values. In addition, the case of entering a single value for parameter values by age group and the case of entering probabilistic distributions were compared and analyzed.

참고문헌 (19)

  1. NSSC, "Criteria for reuse of site and builings after completion of decommissioning of nuclear facilities", Nuclear Safety and Security Commission, ~ (2021)
  2. ANL, "User’s Manual for RESRAD Version 6", Argonne National Laboratory, ~ (2001)
  3. Consolidated decommissioning guidance, characterization, survey, and determination of radiological criteria, "NRC", ~, pp.NUREG-1757 2 (1) (2006)
  4. CYAPC, "HADDAM NECK plant license termination plan Rev. 4", Connecticut yankee atomic power company, ~ (2006)
  5. YAEC, "Yankee nuclear plant station license termination plan, Rev. 1", Yankee Atomic Electric Company, ~ (2004)
  6. SMUD, "Rancho seco license termination plan chapter 6, compliance with the radiological criteria for license termination, Rev. 0", Sacramento Municipal Utility District, ~ (2006)
  7. Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes, "NRC", U.S. Nuclear Regulatory Commission, ~, pp.NUREG (2000), CR-6697
  8. Evaluation of Hydrologic Uncertainty Assessments for Decommissioning Sites Using Complex and Simplified Models, "NRC", ~, pp.NUREG (2002), CR-6767
  9. Probabilistic Dose Analysis Using Parameter Distributions Developed for RESRAD and RESRAD-BUILD Codes, "NRC", U.S. Nuclear Regulatory Commission, ~, pp.NUREG (2000), CR-6676
  10. H. W. Seo, "Proposal for the list of potential radionuclides of interest during NPP site characterization or final status surveys", Nucl. Eng. Technol, 53(1), pp.234~243 (2021)
  11. Radionuclides for consideration during rancho seco site characterization or final status surveys Rev. 2, "SMUD", Sacramento Municipal Utility District, ~ (2005)
  12. H. W. Seo, "The effect of sensitive and non-sensitive parameters on DCGL in probability analysis for decommissioning of nuclear facilities", Nucl. Eng. Technol, pp.3359~3570 (2023)
  13. Development of regulatory requirements for clearance of radioactive waste, "KINS", Korea Institute of Nuclear Safety, ~ (2002)
  14. Supplementation an V&V of integrated dose assessment code package, "KINS", Korea Institute of Nuclear Safety, ~ (2014)
  15. Development of technology in radiation safety regulations, "KINS", Korea Institute of Nuclear Safety, ~ (2005)
  16. ANL, "Data collection handbook to support modeling impacts of radioactive material in soil and building structures", ANL, ~ (2015)
  17. H. W. Seo, "Calculation of preliminary site-specific DCGLs for nuclear power plant decommissioning using hybrid scenarios", Nucl. Eng. Technol, pp.1098~1108 (2019)
  18. Resident exposure dose assessment, "KINS", Korea Institute of Nuclear Safety, ~, pp.KINS (2022), RG-N02.02, Rev. 3
  19. Life time survey results, "S. Korea", Statistics Korea, ~ (2019)

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