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

Korean Radioactive Waste Society (한국방사성폐기물학회)
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A Study on Annual Release Objectives and Annual Release Limits of Gaseous Effluents During Decommissioning of Nuclear Power Plants

원전 해체 시 기체상 유출물의 연간 방출관리치 및 방출한도치에 관한 연구

  • 이승희 (한국전력국제원자력대학원대학교) ;
  • 황원태 (한국원자력연구원) ;
  • 김창락 (한국전력국제원자력대학원대학교)
  • Received : 2019.07.27
  • Accepted : 2019.09.19
  • Published : 2019.09.30
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Abstract

Decommissioning is a critical issue in Korea. Although compared with the operation of nuclear power plants the release of radioactive materials during decommissioning is not expected to be significant, residents should always be protected from radiation exposure. To manage this effectively, Annual Release Objectives (ARO) and Annual Release Limits (ARL) were derived from dose standards in the NSSC Notice and dose limit for the public. Based on meteorological data for the three years from 2008 to 2010 in the Shin Kori nuclear power plant site, atmospheric dispersion and ground deposition factors of gaseous effluent were evaluated using the XOQDOQ computer code. The exposure dose was evaluated using the ENDOS-G computer code. Because of differences in radiological sensitivity according to age groups, the results of Annual Release Objectives (ARO) and Annual Release Limits (ARL) showed significant differences depending on the radionuclides. The evaluation methodology of this study will provide meaningful information for radioactive effluent management for decommissioning of nuclear power plants.

최근 한국에서 원전해체는 중요한 이슈이다. 원전의 운영 시와 비교해볼 때, 원전 해체 시에는 방사성물질의 방출이 크지 않을 것으로 예상되지만, 주민은 항상 방사선피폭으로부터 보호되어야 한다. 이에 대한 효과적인 관리를 위해, 연간 방출관리치와 방출한도치를 원자력안전위원회 고시 및 일반인 선량한도 기준으로부터 유도하였다. 기체상 유출물에 의한 대기 확산 및 침적 인자는 신고리 발전소 기상탑에서 2008년부터 2010년까지 3년간 수집 된 기상자료를 토대로 XOQDOQ 컴퓨터 코드를 이용해서 평가하였다. 선량평가는 ENDOS-G 컴퓨터 코드를 사용하였다. 이 컴퓨터 코드를 이용하여 기체상 유출물의 연간 방출관리치 및 방출한도치를 평가한 결과, 핵종별로 차이가 있었는데, 이는 연령에 따른 방사선민감도의 차이에 기인한다고 할 수 있다. 본 평가 방법 및 결과는 향후 원전 해체 시 방사성유출물 관리에 중요한 정보를 제공할 수 있을 것으로 판단된다.

Keywords

References

  1. Nuclear Safety and Security Commission, Standards for Radiation Protection, etc., NSSC Notice 2019-10 (2019).
  2. U. S. Nuclear Regulatory Commission, Decommissioning of Nuclear Power Reactors, Regulatory Guide 1.184, U. S. NRC, Washington, D.C. (2013).
  3. U. S. Nuclear Regulatory Commission, Long-Lived Activation Products in Reactor Materials, NUREG/CR-3474, U. S. NRC, Washington, D.C. (1984).
  4. International Atomic Energy Agency, Methodologies for Assessing the Induced Activation Source Term for Use in Decommissioning Applications, IAEA Safety Reports Series No.95, IAEA-SRS-95, IAEA, Vienna (2019).
  5. Nuclear Safety and Security Commission, Standards for the Evaluation and Survey on the Weather Conditions at the Site of Nuclear Facility, NSSC Notice 2017-26 (2017).
  6. International Atomic Energy Agency, Prospective Radiological Environmental Impact Assessment for Facilities and Activities, IAEA Safety Standards, General Safety Guide No. GSG-10, IAEA, Vienna (2018).
  7. U. S. Nuclear Regulatory Commission, Meteorological Monitoring Programs for Nuclear Power Plants, Regulatory Guide 1.23, U. S. NRC, Washington, D.C. (2007).
  8. U. S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CR-2919, U. S. NRC, Washington, D.C. (1982).
  9. U. S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors, Regulatory Guide 1.111, U. S. NRC, Washington, D.C. (1977).
  10. Korea Advanced Energy Research Institute, Environmental Impact Assessment and Development of Related Models around Kori Nuclear Power Plants: Guide to Evaluated Off-site Radiological Dose, Appendix X, KAERI/NSC-397/89 (1989).
  11. U. S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Regulatory Guide 1.109, U. S. NRC, Washington, D.C. (1976)
  12. International Commission on Radiological Protection, The 1990 Recommendations of the International Commission on Radiological Protection, ICRP Publication 60, ICRP (1990).
  13. E.H. Kim, W.T. Hwang, M.H. Han, and H.J. Jeong, Handbook of Dose Coefficients v2.54, Korea Atomic Energy Research Institute (2008).