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변지향,박상준,안석영 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.8
Preliminary surface soil Derived Concentration Guideline Levels (DCGLs) were derived conforming to theMulti-Agency Radiation Site Survey and Investigation Manual (MARSSIM) procedure for the site releaseand reuse of Kori Unit 1 in Korea. Based on the decommissioning experiences of the U.S. nuclear powerplants, a suite of residual radionuclides was determined, and uncertainties contributed to the resultantdose by the input parameters were quantified via the sensitivity analysis of parameters. The peak of themean dose was obtained via the probabilistic analysis of the RESRAD (RESidual RADioactivity)-ONSITEcode. Consequently, DCGLw of Kori Unit 1 in accordance with two scenarios, industrial worker andresidential farmer scenario, were derived and the results were compared respectively with other NPPs. Itcould be used as a basic guideline for establishing regulatory standards for reuse planning, designing thesite characterization surveys and implementing final status survey (FSS).
변지향,박상준,김양진,안석영 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.5
The containment building Kori Unit 1 may require sequential steps for full decommissioning. This studyassumes that the containment building is to be used as an auxiliary building that handles nuclear powersystems and materials during decommissioning before conversion into a greenfield. Through the derivation of guidelines and dose evaluation, it was confirmed whether the radiation workers were satisfiedwith the ALARA decision. The specific modeling of the external radiation exposure was performed basedon the facility investigation procedures. The external radiation specific derived concentration guidelinelevels (DCGLs) for radiation workers in containment building were obtained using the RESRAD-BUILDcode and were applied to the VISIPLAN 3D ALARA Planning Tool code to calculate the working doseand check worker safety. The derivation of site-specific and realistic DCGLs and dose evaluation via 3Dmodeling can contribute to the scenario development for the decommission and remediation ofcontainment building
고리1호기 증기발생기 제염해체 시 작업자 피폭선량 평가 및 저감화 방안
손영직,박상준,변지향,안석영,Son, Young Jik,Park, Sang June,Byon, Jihyang,Ahn, Seokyoung 한국방사성폐기물학회 2018 방사성폐기물학회지 Vol.16 No.3
Korea's first commercial nuclear power plant, Kori Unit 1, was permanently shut down on June 18, 2017, after 40 years of successful operation. Kori Unit 1 plans to construct a waste treatment facility in the turbine building prior to commencement of dismantling in earnest. Various radioactive wastes are decontaminated, disassembled, cut and melted in the waste treatment facility and sent to the radioactive waste repository. The proportion of metal radioactive waste in dismantled waste is about 70%, of which large metal radioactive waste is mainly generated in the primary circuit and has high radioactivity, so radiation exposure must be managed during disassembly. In this study, the steam generators are selected as large metal radioactive waste, the exposure doses of the dismantling workers are calculated using RESRAD-RECYCLE code and the methods for reducing the exposure doses are suggested.