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Proposal for the list of potential radionuclides of interest during NPP site characterization or final status surveys

  • Seo, Hyung-Woo (Department of Mechanical Engineering, Chungnam National University) ;
  • Oh, Jae Yong (Korea Hydro & Nuclear Power (KHNP) Central Research Institute) ;
  • Shin, Weon Gyu (Department of Mechanical Engineering, Chungnam National University)
  • Received : 2020.02.18
  • Accepted : 2020.06.05
  • Published : 2021.01.25

Abstract

In the research or project planning for the decommissioning of a nuclear power plant, one of several preparations will be the establishment of a list of potential radionuclides to be considered at the time of characterization or final status surveys. Reliable data for selection of potential radionuclides during the transition period to prepare for decommissioning will depend heavily on historical data at the site or, where possible, sampling analysis. However, during the transition period, direct sampling can be challenging, depending on the circumstances of the site or national regulation. A methodology of selecting potential radionuclides for nuclear facility sites which largely consists of three major processes: production of initial list of radionuclides, selection of the insignificant radionuclide that will be eliminated, and consideration of site characterization or sampling. For developing a preliminary list of potential radionuclides for Kori Unit 1 decommissioning, the list of initial radionuclides was made referring to the technical documents applied at decommissioned NPPs in the U.S and additional reference materials applied until the operation of NPPs in Korea. For the screening of insignificant radionuclides, we applied criterion of less than 0.1% of the amount of radioactivity inventory and confirmed the dose fraction using the RESRAD code. The final suit of radionuclides was established, which should be supplemented by reflecting site characterization and sampling process in the future. Thus, the methodology and results for the selection of potential radionuclides suggested in this paper can give an insight as a future reference to deriving DCGLs in relation to site remediation of decommissioning nuclear plants.

Keywords

References

  1. U.S. Environmental Protection Agency, What is a derived concentration guideline level (DCGL)? [Internet] Accessed, https://epa.gov/radiation/what-derived-concentration-guideline-level-dcgl, 2020. Available from:.
  2. H.W. Seo, W. Sohn, Calculation of preliminary site-specific DCGLs for nuclear power plant decommissioning using hybrid scenarios, Nucl. Eng. Technol. 51 (4) (2019) 1098-1108. https://doi.org/10.1016/j.net.2019.01.018
  3. J. Byon, S. Park, S. Ahn, Derivation of preliminary derived concentration guideline levels for surface soil at Kori Unit 1 by RESRAD probabilistic analysis, Nucl. Eng. Technol. 50 (8) (2018) 1289-1297. https://doi.org/10.1016/j.net.2018.07.018
  4. H.W. Seo, W. Sohn, Scenario options to calculation of Derived Concentration Guideline Levels for a multi-unit decommissioning site, Ann. Nucl. Energy 133 (2019) 347-358. https://doi.org/10.1016/j.anucene.2019.05.036
  5. U.S. Nuclear Ragulatory Commission, Multi-agency radiation survey and site investigation manual (MARSSIM), NUREG-1575, Rev 1 (2000).
  6. ZionSolutions, Technocal support document for potential radionuclides of concern during the decommissioning of the zion station, Rev 1 (2012).
  7. Pacific Gas, Electric Company, Radionuclide Selection for, DCGL Development, 2012.
  8. Sacramento Municipal Utility District, Radionucldies for Consideration during Rancho Seco Site Characterization or Final Status Surveys, 2005.
  9. U.S. Nuclear Ragulatory Commission, Long-Lived Activation Products in Reactor Materials, NUREG/CR-3474, 1984.
  10. U.S. Nuclear Ragulatory Commission, Residual Radionuclide Contamination within and Around Commercial Nuclear Power Plants, NUREG/CR-4289, 1986.
  11. N.C. Dyer, T.E. Bechtold, Radionuclides in United States Commercial Nuclear Power Reactors, WINCO-1191, IDAHO National Engineering Laboratory, 1994.
  12. U.S. Nuclear Ragulatory Commission, Technology, Safety and Cost of Decommissioning a Reference Pressurized Water Reactor Power Station, vol. 1, NUREG/CR-0130, 1978.
  13. Nuclear Safety and Security Commission, Regulations for the Management of Low and Intermediate Level RadioactiveWaste, Notice No. 2017-65, 2017 (In Korean).
  14. Korea Atomic Energy Research Institute, Table of nuclides [Internet] Accessed 2019, Available from: http://atom.kaeri.re.kr/nuchart.
  15. Nuclear Safety and Security Commission, Criteria for Reuse of Site and Builings after Completion of Decommissioning of Nucelar Facilities, Notice No. 2016-33, 2016 (In Korean).
  16. Argonne National Laboratory, User's Manual for RESRAD Version 6, ANL/EAD-4, 2001.
  17. Argonne National Laboratory, Data Collection Handbook to Support Modeling Impacts of Radioactive Material in Soil and Building Structures, 2015.
  18. Korea Institute of Nuclear Safety, Development of Regulatory Requirements for Clearance of Radioactive Waste, KINS/RR-144, 2002.
  19. Korea Institute of Nuclear Safety, Development of Technology in Radiation Safety Regulations, KINS/GR-297, 2005.
  20. Korea Institute of Nuclear Safety, Supplementation an V&V of Integrated Dose Assessment Code Package, KINS/HR-1357, 2014.
  21. Rancho Seco Nuclear Generating Station, Comparison of dose impacts from alternative exposure scenarios, Rev 0 (2005).
  22. U.S. Nuclear Regulatory Commission, Consolidated decommissioning guidance, characterization, survey, and Determination of radiological criteria, NUREG-1757, Rev 1 (2006).
  23. Electric Power Research Institute, Connecticut Yankee Decommissioning Expereience Report, Detailed Experiences 1996-2006, 2006.
  24. Electric Power Research Institute, San Onofre Nuclear Generating Station Unit 1 Decommissioning Experience Report Detailed Experiences 1999-2008, 2008.
  25. Yankee Nuclear Power Station, Yankee nuclear plant station license termination plan, Rev 1 (2004).