Earticle

초록

영어

Background: Interfacing-system loss-of-coolant-accident (ISLOCA) has been identified as the most hazardous accident scenario in the typical PWR plants. The present study as an effort to improve the knowledge of the source term to the environment during ISLOCA focuses on an improvement of the estimation method. Materials and Methods: The improvement was performed to take into account an effect of broken pipeline and auxiliary building structures relevant to ISLOCA. An estimation of the source term to the environment was for the OPR-1000 plants by MELOCR code version 1.8.6. Results and Discussion: The key features of the source term showed that the massive amount of fission products departed from the beginning of core degradation to the vessel breach. Conclusion: The release amount of fission products may be affected by the broken pipeline and the auxiliary building structure associated with release pathway.

목차

ABSTRACT
 Introduction
 Materials and Methods
  1. Characterizing ISLOCA
  2. MELCOR modeling
 Results and Discussion
  1. Plant transient behavior
  2. Source term
 Conclusion
 Acknowledgements
 References

키워드

저자

• Seok-Jung Han [ Risk and Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon, Korea ] Corresponding author
• Tae-Woon Kim [ Risk and Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon, Korea ]
• Kwang-Il Ahn [ Risk and Environmental Safety Research Division, Korea Atomic Energy Research Institute, Daejeon, Korea ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  방사선방어학회지 [Journal of Radiation Protection and Research]

• 간기

  계간

• pISSN

  2508-1888

• 수록기간

  1976~2026

• 등재여부

  KCI 등재,SCOPUS

• 십진분류

  KDC 559 DDC 629