Nuclear Engineering and Technology

  • 제44권7호
  • /
  • Pages.745-754
  • /
  • 2012
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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A STUDY ON METHODOLOGY FOR IDENTIFYING CORRELATIONS BETWEEN LERF AND EARLY FATALITY

  • Kang, Kyungmin (Department of Nuclear Engineering, Hanyang University) ;
  • Jae, Moosung (Department of Nuclear Engineering, Hanyang University) ;
  • Ahn, Kwang-Il (Korea Atomic Energy Research Institute)
  • 투고 : 2011.06.28
  • 심사 : 2012.01.03
  • 발행 : 2012.10.25
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초록

The correlations between Large Early Release Frequency (LERF) and Early Fatality need to be investigated for risk-informed application and regulation. In Regulatory Guide (RG) -1.174, while there are decision-making criteria using the measures of Core Damage Frequency (CDF) and LERF, there are no specific criteria on LERF. Since there are both huge uncertainties and large costs needed in off-site consequence calculation, a LERF assessment methodology needs to be developed, and its correlation factor needs to be identified, for risk-informed decision-making. A new method for estimating off-site consequence has been presented and performed for assessing health effects caused by radioisotopes released from severe accidents of nuclear power plants in this study. The MACCS2 code is used for validating the source term quantitatively regarding health effects, depending on the release characteristics of radioisotopes during severe accidents. This study developed a method for identifying correlations between LERF and Early Fatality and validates the results of the model using the MACCS2 code. The results of this study may contribute to defining LERF and finding a measure for risk-informed regulations and risk-informed decision-making.

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참고문헌

  1. W. T. Pratt, V. Mubayi, T.L. Chu, "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events," U.S. Nuclear Regulatory Commission, NUREG/CR-6595, 2004.
  2. A. L. Hanson, R. E. Davis, V. Mubayi, "Calculations in Support of a Potential Definition of Large Release," U.S. Nuclear Regulatory Commission, NUREG/CR-6094, 1994.
  3. Davis, R. E., A. L. Hanson, and V. Mubayi, "Reassessment of Selected Factors Affecting Siting of Nuclear Power Plants," NUREG/CR-6295, BNL-NUREG-52442, Brookhaven National Laboratory, February 1997.
  4. Sherry, R., "Considerations for Plant - Specific Site - Specific Application of Safety Goals and Definition of Subsidiary Criteria," Memorandum to ACRS Members, June 27, 1997.
  5. KEPCO, "UCN Units 3&4 Final Probabilistic Safety Assessment Report," Korea Electric Power Cooperation, 1998.
  6. KOPEC, "Probabilistic Safety Assessment for Ulchin Units 3&4," Korea Electric Power Cooperation, 2004.
  7. Kaiser, G. D., "The Implications of Reduced Source Terms for Ex-Plant Consequence Modeling," ANS Executive Conference on the Ramifications of the Source Term, March 12, 1985, Charleston, SC.
  8. USNRC, "Safety Goals for the Operation of Nuclear Power Plants; Policy Statement," Federal Register, Vol. 51, No. 149, U.S. Nuclear Regulatory Commission, August 4, 1986.
  9. USNRC, "Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants," U.S. Nuclear Regulatory Commission, WASH-1400, 1975.
  10. USNRC, "Severe Accident Risks: An assessment for Five U.S. Nuclear Power Plants," U.S. Nuclear Regulatory Commission, NUREG-1150, 1989.
  11. John R. Lamarsh, Anthony J. Baratta, "Introduction to Nuclear Engineering" Prentice Hall 2001.
  12. J.J. DiNunno et al., "Calculation of Distance Factors for Power and Test Reactor Sites" Technical Information Documents (TID)-14844, U.S. Atomic Energy Commission 1962.
  13. D.I. Chanin and L.A. Miller, "MACCS2: An Improved Code for Assessing Nuclear Accident Consequences," SAND97-0594, 1997.
  14. L.T. Ritchie. D.I. Chanin, J.L. Sprung, L.T. Ritchie, and H.N. Jow, "MELCOR Accident Consequence Code System," U.S. Nuclear Regulatory Commission, NUREG/CR-4691, 1990.
  15. L. Neymotin, "Comparisons of MACCS Users Calculations for the International Comparison Exercise on Probabilistic Consequence Assessment Codes," NUREG/CR-6053, Brookhaven National Laboratory, 1994.