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Study on Dose Rate on the Surface of Cask Packed with Activated Cut-off Pieces from Decommissioned Nuclear Power Plant

방사선방어학회지 2020년 45권 4호 p.178 ~ 186
박광수, 김해웅, Sohn Hee-Dong, 김남균, 이정규, 이윤, 이지훈, 황영환, 이미현, 이동규, 정덕운,
소속 상세정보
박광수 ( Park Kwang-Soo ) - Doosan Heavy Industries and Construction Nuclear Decommissioning Technology and Business Development Team
김해웅 ( Kim Hae-Woong ) - Doosan Heavy Industries and Construction Nuclear Decommissioning Technology and Business Development Team
 ( Sohn Hee-Dong ) - Doosan Heavy Industries and Construction Nuclear Decommissioning Technology and Business Development Team
김남균 ( Kim Nam-Kyun ) - KEPCO KPS RAF Team
이정규 ( Lee Chung-Kyu ) - KEPCO KPS RAF Team
이윤 ( Lee Yun ) - KEPCO KPS RAF Team
이지훈 ( Lee Ji-Hoon ) - Korea Hydro and Nuclear Power Co. Ltd. Radiation and Environmental Laboratory
황영환 ( Hwang Young-Hwan ) - Korea Hydro and Nuclear Power Co. Ltd. Radiation and Environmental Laboratory
이미현 ( Lee Mi-Hyun ) - Korea Hydro and Nuclear Power Co. Ltd. Radiation and Environmental Laboratory
이동규 ( Lee Dong-Kyu ) - KONES Corporation Nuclear Energy Team
정덕운 ( Jung Duk-Woon ) - KONES Corporation Nuclear Energy Team

Abstract


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.

키워드

Monte Carlo; Cask; Drum; Reactor Pressure Vessel; Internal; Decommissioning

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