Earticle

초록

영어

Background: Reactor pressure vessel (RV) with internals (RVI) are activated structures by neutron irradiation and volume contaminated wastes. Thus, to develop safe and optimized disposal plan for them at a disposal site, it is important to perform exact activation calculation and evaluate the dose rate on the surface of casks which contain cut-off pieces. Materials and Methods: RV and RVI are subjected to neutron activation calculation via Monte Carlo methodology with MCNP6 and ORIGEN-S program—neutron flux, isotopic specific activity, and gamma spectrum calculation on each component of RV and RVI, and dose rate evaluation with MCNP6. Results and Discussion: Through neutron activation analysis, dose rate is evaluated for the casks containing cut-off pieces produced from decommissioned RV and RVI. For RV cut-off ones, the highest value of dose rate on the surface of cask is 6.97 × 10-1 mSv/hr and 2 m from it is 3.03 × 10-2 mSv/hr. For RVI cut-off ones, on the surface of it is 0.166 × 10-1 mSv/hr and 2 m from it is 1.04 × 10-1 mSv/hr. Dose rates for various RV and RVI cut-off pieces distributed lower than the limit except the one of 2 m from the cask surface of RVI. It needs to adjust contents in cask which carries highly radioactive components in order to decrease thickness of cask. Conclusion: Two types of casks are considered in this paper: box type for very-low-level waste (VLLW) as well as low-level waste (LLW) and cylinder type for intermediate-level waste (ILW). The results will contribute to the development of optimal loading plans for RV and RVI cut-off pieces during the decommissioning of nuclear power plant that can be used to prepare radioactive waste disposal plans for the different types of wastes—ILW, LLW, and VLLW.

목차

ABSTRACT
Introduction
Materials and Methods
1. Cutting Procedure and Loading Strategy
Results and Discussion
1. Dose Rate Evaluation of Cask for RV and RVI Cut-off Pieces
Conclusion
References

키워드

저자

• Kwang Soo Park [ Nuclear Decommissioning Technology & Business Development Team, Doosan Heavy Industries and Construction, Changwon, Korea ] Corresponding Author
• Hae Woong Kim [ Nuclear Decommissioning Technology & Business Development Team, Doosan Heavy Industries and Construction, Changwon, Korea ]
• Hee Dong Sohn [ Nuclear Decommissioning Technology & Business Development Team, Doosan Heavy Industries and Construction, Changwon, Korea ]
• Nam Kyun Kim [ RAF Team, KEPCO KPS, Naju, Korea ]
• Chung Kyu Lee [ RAF Team, KEPCO KPS, Naju, Korea ]
• Yun Lee [ RAF Team, KEPCO KPS, Naju, Korea ]
• Ji Hoon Lee [ Radiation & Environmental Laboratory, Korea Hydro & Nuclear Power Co. Ltd., Daejeon, Korea ]
• Young Hwan Hwang [ Radiation & Environmental Laboratory, Korea Hydro & Nuclear Power Co. Ltd., Daejeon, Korea ]
• Mi Hyun Lee [ Radiation & Environmental Laboratory, Korea Hydro & Nuclear Power Co. Ltd., Daejeon, Korea ]
• Dong Kyu Lee [ Nuclear Energy Team, KONES Corporation, Seoul, Korea ]
• Duk Woon Jung [ Nuclear Energy Team, KONES Corporation, Seoul, 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