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한국과 미국의 원전 중대사고 시 소외 사고결말평가 시스템 비교 연구

Comparative Study of Off-site Consequence Assessment System of Nuclear Power Plant Severe Accident in Korea and U.S.

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Having experienced the TMI, the Chernobyl, and the Fukushima accident, NPPs are beingforced to follow stricter safety procedures. Korea and the US are using S-REDAP and RASCAL offsiteconsequence assessment systems based on relevant laws. In accordance with the Act on PhysicalProtection and Radiological Emergency, domestic NPP operators use the assessment system to determineemergency resident protection measures. For accurate resident protection measures, high reliability ofthe domestic consequence assessment system and methodology is important. The purpose of this studyis to compare methodologies of consequence assessment systems in Korea and US and to compare andanalyze assessment results. In this case, the result comparison analysis used an assessment code thatuses the domestic consequence assessment methodology. To achieve this, first, the methodologies of thetwo countries were compared. Second, a simulation scenario was established. Finally, assessment wasconducted based on the simulated scenario. It was found that there are differences in the source termassessment in the inventory and radioactive decay method, the core emission fraction applied unit, and thecore damage input method. In the atmospheric diffusion assessment, the diffusion model was the same asthe Gaussian model, but the domestic assessment models were AERMOD and CALPUFF, and the US wasTADPLUME and TADPUFF. In the dose assessment, there were differences in the duration of the derivedresults and the dose conversion factor. The simulation scenario was set as a scenario in which radioactivematerial was released outside the NPP, and the leakage rate at the time of release was set at 5% hr-1, andthe core damage was set at 5% of the core melt. As a result of the total emission amount, assessment codewas evaluated 1.8 times more conservatively than RASCAL. The initial dose was evaluated 5 to 9 times moreconservatively on assessment code, and 2 to 4 times more conservatively on RASCAL for the mid- to longtermdose. The initial dose was due to the difference between the emission amount and the assessmentperiod, and the mid- to long-term dose was considered to be due to the difference in the terrain effect. The results of this study are expected to prove the reliability of domestic accident assessment system andmethodologies and to be used in the prediction of doses in case of severe accidents.

Abstract

Having experienced the TMI, the Chernobyl, and the Fukushima accident, NPPs are beingforced to follow stricter safety procedures. Korea and the US are using S-REDAP and RASCAL offsiteconsequence assessment systems based on relevant laws. In accordance with the Act on PhysicalProtection and Radiological Emergency, domestic NPP operators use the assessment system to determineemergency resident protection measures. For accurate resident protection measures, high reliability ofthe domestic consequence assessment system and methodology is important. The purpose of this studyis to compare methodologies of consequence assessment systems in Korea and US and to compare andanalyze assessment results. In this case, the result comparison analysis used an assessment code thatuses the domestic consequence assessment methodology. To achieve this, first, the methodologies of thetwo countries were compared. Second, a simulation scenario was established. Finally, assessment wasconducted based on the simulated scenario. It was found that there are differences in the source termassessment in the inventory and radioactive decay method, the core emission fraction applied unit, and thecore damage input method. In the atmospheric diffusion assessment, the diffusion model was the same asthe Gaussian model, but the domestic assessment models were AERMOD and CALPUFF, and the US wasTADPLUME and TADPUFF. In the dose assessment, there were differences in the duration of the derivedresults and the dose conversion factor. The simulation scenario was set as a scenario in which radioactivematerial was released outside the NPP, and the leakage rate at the time of release was set at 5% hr-1, andthe core damage was set at 5% of the core melt. As a result of the total emission amount, assessment codewas evaluated 1.8 times more conservatively than RASCAL. The initial dose was evaluated 5 to 9 times moreconservatively on assessment code, and 2 to 4 times more conservatively on RASCAL for the mid- to longtermdose. The initial dose was due to the difference between the emission amount and the assessmentperiod, and the mid- to long-term dose was considered to be due to the difference in the terrain effect. The results of this study are expected to prove the reliability of domestic accident assessment system andmethodologies and to be used in the prediction of doses in case of severe accidents.

참고문헌 (23)

  1. U.S. NRC, "Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents" (1988), U.S. Nuclear Regulatory Commission
  2. U.S. NRC, "RTM-96, Response Technical Manual" (1996), U.S. Nuclear Regulatory Commission
  3. U.S. NRC, "RASCAL 3.0: Description of Models and Methods" (2001), U.S. Nuclear Regulatory Commission
  4. U.S. NRC, "RASCAL 4.0: Description of Models and Methods" (2012), U.S. Nuclear Regulatory Commission
  5. "Law No. 10910. Act on Physical Protection and Radiological Emergency", ~ (2011)
  6. "Presidential Decree No. 23248. Enforcement Decree of Act on Physical Protection and Radiological Emergency", ~ (2011)
  7. "Ministry of Science and Technology Decree No. 1. Enforcement Rule of Act on Physical Protection and Radiological Emergency", ~ (2008)
  8. KEPCO E&C, "Radiation Dose Assessment for Recommendation of Resident Protection Measures in a Radiation Emergency" (2006)
  9. KHNP, "Development of an Integrated System for Assessment of Radiation Dose in case of a Nuclear Accident" (2015)
  10. Yang YH, "Comparative Analysis of the Evaluation of Source Terms to Reflect SREDAP in case of LTSBO Severe Accident", Proceedings of the Korean Radioactive Waste Society Conference, pp.517~518 (2015)
  11. Borhan Uddin Gazi Muhammad, "Nuclear Emergency Management using Accident Consequence Analysis Code", 한국방재학회논문집, 19(4), pp.215~225 (2019), 한국방재학회[DOI]
  12. 이진오, "원전 사고 시 RASCAL과 HYSPLIT 전산코드를 이용한 대기확산 모델별 방사성물질의 지표면 침적농도 분석", 방사선산업학회지, 13(2), pp.163~171 (2019), (사)한국방사선산업학회[DOI]
  13. U.S. NRC, "Accident Source Terms for Light Water Nuclear Power Plants" (1995), U.S. Nuclear Regulatory Commission
  14. Fukushima Nuclear Accident Analysis Final Report, "KNS Committee on the Fukushima Accident", ~ (2013)
  15. Final Report on the Establishment of a Radioactive Disaster Prevention Training System for Nuclear Accident in Neighboring Countries, "Nuclear Safety and Security Commission", ~ (2019)
  16. "Meteorological Agency Comprehensive Climate Change Monitoring Information"[URL]
  17. Shin-Kori Units 1 and 2, Final Safety Analysis Report, "KHNP", ~ (2018)
  18. EPA, "A User’s Guide for the CALPUFF Dispersion Model" (2000), U.S. Environmental Protection Agency
  19. EPA, "AERMOD: Description of model formulation" (2004), U.S. Environmental Protection Agency
  20. EPA, "Federal Guidance Report No.12: External Exposure to Radionuclides in Air, Water, and Soil" (1993), U.S. Environmental Protection Agency
  21. EPA, "Federal Guidance Report No.13: Cancer Risk Coefficients for Environmental Exposure to Radionuclides" (1999), U.S. Environmental Protection Agency
  22. ICRP, "Dose Coefficients for Intakes of Radionuclides by Workers" (1994)
  23. ICRP, "Age-dependent Doses to the Members of the Public from Intake of Radionuclides: Part 5 Compilation of Ingestion and Inhalation Coefficients" (1995)

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