• Title/Summary/Keyword: 제염해체공사

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Development of Risk Breakdown Structure of Nuclear Power Plant Decommissioning Project: Focusing on Structural Damage / Work Process Risks (원전 차폐 콘크리트 구조물 제염해체공사 리스크 분류체계 구축: 구조적 / 작업 리스크를 중심으로)

  • Kim, Byeol;Lee, Joo-Sung;Ahn, Yong-Han
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.22 no.3
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    • pp.38-45
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    • 2018
  • The purpose of this study is to deduct the structural damage / work process risks factors which can be occurred during the decommissioning in the NPP containment concrete structure. To achieve these purpose, risk profile specified in the construction industry is analyzed, and the work process of NPP decommissioning and the construction project were matched based on the similarity of each works. Accordingly, human and physical risk factors are classified. Finally, the risk associated with the building structure and work process was classified as per their process activities, and risk typology explaining the disaster which put the structure, equipments, machine and workers in serious danger was developed.

Evaluation of Residual Radiation and Radioactivity Level of TRIGA Mark-II, III Research Reactor Facilities for Safe Decommissioning (TRIGA Mark-II, III 연구로 시절의 폐로를 위한 시설의 잔류 방사선/능 평가)

  • Lee, B.J.;Chang, S.Y.;Park, S.K.;Jung, W.S.;Jung, K.J.
    • Journal of Radiation Protection and Research
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    • v.24 no.2
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    • pp.109-120
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    • 1999
  • Residual radiation and radioactivity level in TRIGA Mark-II, III research reactors and facilities at the KAERI Seoul site, which are to be decommissioned, have been measured, analyzed and evaluated to know the current status of radiation and radioactivity level and to establish and to provide the technical requirements for the safe decommissioning of the facilities which shall be applied in minimizing the radiation exposure for workers and in preventing the release of the radioactive materials to the environment. Radiation dose rate and surface radioactivity contamination level on the experimental equipments, floors, walls of the facilities, and the surface of the activated materials within the reactor pool structure were measured and evaluated. Radioactivity and radionuclides in the pool and cooling water were also analyzed. In case of the activated reactor pool structures which are very difficult to measure the radiation and radioactivity level, a computer code Fispin was additionally used for estimation of the residual radioactivity and radionuclides. The radiation and radioactivity data obtained in this study were effectively used as basic data for decontamination and dismantling plan for safe decommissioning of TRIGA Mark-II, III facilities.

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