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
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