Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 14(4); 2016
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2016;14(4):423-434. Published online: Dec, 30, 2016

Study on the Code System for the Off-Site Consequences Assessment of Severe Nuclear Accident

  • Sora Kim ; Byung-Il Min ; Kihyun Park ; Byung-Mo Yang ; Kyung-Suk Suh
Abstract

The importance of severe nuclear accidents and probabilistic safety assessment (PSA) were brought to international attention with the occurrence of severe nuclear accidents caused by the extreme natural disaster at Fukushima Daiichi nuclear power plant in Japan. In Korea, studies on level 3 PSA had made little progress until recently. The code systems of level 3 PSA, MACCS2 (MELCORE Accident Consequence Code System 2, US), COSYMA (COde SYstem from MAria, EU) and OSCAAR (Off-Site Consequence Analysis code for Atmospheric Releases in reactor accidents, JAPAN), were reviewed in this study, and the disadvantages and limitations of MACCS2 were also analyzed. Experts from Korea and abroad pointed out that the limitations of MACCS2 include the following: MACCS2 cannot simulate multi-unit accidents/release from spent fuel pools, and its atmospheric dispersion is based on a simple Gaussian plume model. Some of these limitations have been improved in the updated versions of MACCS2. The absence of a marine and aquatic dispersion model and the limited simulating range of food-chain and economic models are also important aspects that need to be improved. This paper is expected to be utilized as basic research material for developing a Korean code system for assessing off-site consequences of severe nuclear accidents.

Keywords

MACCS2,COSYMA,OSCAAR,Level 3 Probabilistic Safety Assessment,Off-site consequence assessment,Severe nuclear accident