원자력발전소 중대사고시 소외결말분석상에 방사선원항 특성의 영향 = Effects of Radiological Source Term Characteristics on Off-site Consequence Analysis owing to Severe Accident of Nuclear Power Plant

다국어 초록 (Multilingual Abstract)

The effects of the radiological source term characteristics on an off-site consequence analysis owing to severe accident of a unclear power plants have been examined. The typical source tem features, i.e., (1) plume characteristics of release time and duration, (2) aerosol size, and (3) sensible heat, were derived from the MELCOR code as a severe accident code. Their effects on off-site consequence were examined according to a sensitivity analysis approach for each parameter. The results showed that the release time and duration had a considerable effect on a consequence, but the aerosol size and the sensible heat had a limited effect. Based on the obtained insights, it is recommended that it is necessary to apply the source term features to consequence analysis. A further study is recommended to utilize this key finding for a precise estimation of the source term.

참고문헌 (Reference)

1 Soo-Dong Suk, "The state of the art of Source Term" 18 (18): 137-150, 1986

2 Soo-Dong Suk, "The state of the art of Source Term" 18 (18): 137-150, 1986

3 U.S.NRC, "State-of-the-Art Reactor Consequence Analysis (SOARCA) Report" 2012

4 U.S.NRC, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants-Final Summary Report, Vol.1-3" U.S.NRC 1990

5 U.S.NRC, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants-Final Summary Report, Vol.1-3" U.S.NRC 1990

6 U.S. NRC, "Reactor Safety Study-An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants" U.S. Nuclear Regulatory Commission 1975

7 U.S. NRC, "Reactor Safety Study-An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants" U.S. Nuclear Regulatory Commission 1975

8 K. McFadden, "MELMACCS Model Documents, In MELMACCS Install Program" 2011

9 Haste, T., "MELCOR/MACCS Simulation of the TMI-2 Severe Accident and Initial Recovery Phases, Off-site Fission Product Release and Consequences" 26 : 1099-1112, 2006

10 한석중, "MELCOR 코드를 이용한 원자력발전소 중대사고 방사선원항 평가 방법" 한국안전학회 26 (26): 192-204, 2012

11 Gauntt, R.O., "MELCOR Computer Code Manuals, Vol. 1: Primer and Users' Guide, Version 1.8.6, Vol. 1., Rev. 3" Sandia National Laboratories 2005

12 D.I. Chanin, "MELCOR Accident consequence Code System (MACCS), Volume 1 & 2" Sandia National Laboratories 1990

13 Fukushima Committee of Korean Nuclear Society, "An Analysis of the Fukushima Nuclear Plants Accident(Summary)-Draft" Korean Nuclear Society 2012

14 U.S. NRC, "Accident Source Term for Light-Water Nuclear Power Plants" 1995

15 KOPEC, "AOT/STI Relaxation Study for Korean Standard Nuclear Power Plants" The Ministry of Commerce Industry and Energy 2004