A Study on the Effect of Containment Filtered Venting System to Off-site under Severe Accident

중대사고시 격납건물여과배기계통(CFVS)적용으로 인한 사고영향과 결과 고찰

  • Received : 2015.07.10
  • Accepted : 2015.12.11
  • Published : 2015.12.31


The containment filtered venting system reduces the range of the contamination area around the nuclear power plant by strengthening the integrity of the containment building. In this study, the probabilistic assessment code MACCS2 was used to assess the effect of the CFVS to off-site. The accident source term was selected from a Probabilistic Safety Analysis report of SHINKORI 1&2 Nuclear Power Plant. The three source term categories from 19 STC were chosen to evaluate the effective dose and thyroid dose of residents around the power plant and the dose with CFVS and without CFVS were compared. The dose was calculated according to the distance from the nuclear power plant, so the damage scale based on the distance that exceeds the IAEA criteria for effective dose (100 mSv per 7 days) and thyroid dose (50 mSv per 7 days) were compared. The effective dose reduction rates of the STC-3, STC-4, STC-6 were about 95-99% in the whole range (0~35 km), 96-98% for the thyroid dose. There are similar results between effective dose and thyroid dose. After applying the CFVS, the damage scale that exceeds the effective dose criteria was about 1 km (mean). Especially, the STC-4 damage scale was decreased from 26 km (mean) to 1.2 km (mean) significantly. The damage scale that exceed the thyroid dose criteria was decreased to 2~3 km (mean). The STC-4 damage scale was also decreased significantly as compared to STC-3, STC-6 in terms of effective dose.


  1. International Nuclear Safety Advisory Group. Defence in depth in nuclear safety. IAEA-INSAG-10. 1996.
  2. Hillrichs C, Vignon D, Felten P. Review of european filtered containment venting systems. European Nuclear Society(ENS). 2012 December 9-12. Manchester. United Kingdom.
  3. Nuclear Energy Agency. Status report on filtered containment venting. NEA/CSNI/ R(2014)7. 2014.
  4. Chanin D, Young M. Code manual for MACCS2: volume 1 user's guide. Sandia National Laboratories SAND97-0594. 1997.
  5. Bowman S, Gauld I. OrigenArp primer: how to perform isotopic depletion and decay calculations with SCALE/ORIGEN. Oak Ridge National Laboratory ORNL/TM-2010/43. 2010.
  6. U.S. Department Of Energy. MACCS2 Computer Code Application Guidance for Documented Safety Analysis. U.S. Department Of Energy DOE-EH- Guidance. 2004.
  7. Jeon In Young. Study of evaluation methodology for radiological emergency planning zone of nuclear power plants. Doctoral Dissertation, Hanyang University (2004).
  8. International Atomic Energy Agency. Criteria for Use in Preparedness and Response for a Nuclear of Radiological Emergency. IAEA Safety Standards Series No. GSG-2. 2011.