• 방사성폐기물학회지
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• 제21권2호
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• pp.255-269
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• 2023

Compared to operational wastes, nuclear power plant (NPP) decommissioning wastes are generated in larger quantities within a short time and include diverse types with a wider range of radiation characteristics. Currently used 200 L drums and IP-2 type transport containers are inefficient and restrictive in packaging and transporting decommissioning wastes. Therefore, new packaging and transport containers with greater size, loading weight, and shielding performance have been developed. When transporting radioactive materials, radiological safety should be assessed by reflecting parameters such as the type and quantity of the package, transport route, and transport environment. Thus far, safety evaluations of radioactive waste transport have mainly targeted operational wastes, that have less radioactivity and a smaller amount per transport than decommissioning wastes. Therefore, in this study, the possible radiation effects during the transport from NPP to disposal facilities were evaluated to reflect the characteristics of the newly developed containers and decommissioning wastes. According to the evaluation results, the exposure dose to transport workers, handling workers, and the public was lower than the domestic regulatory limit. In addition, all exposure dose results were confirmed, through sensitivity analysis, to satisfy the evaluation criteria even under circumstances when radioactive materials were released 100% from the container.

• 핵의학기술
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• 제14권2호
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• pp.128-132
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• 2010

핵의학과 종합조작실은 방사선 관리구역으로 이곳에서 발생된 방사성오염물질은 방사성폐기물로 간주하여 일반쓰레기와 별도로 관리를 해야 한다. 본 실험은 우리가 미처 인식하지 못해 일반쓰레기로 처분되었던 방사성오염물질의 오염도를 측정하고 원인을 분석하여 보다 적극적인 방사성폐기물 관리 운영의 필요성을 제시하고자 함이다. 측정대상은 방사성의약품을 표지하기 위해 사용된 생리식염수와 $^{99}Mo$/$^{99m}Tc$ generator(국산 및 외산)에서 발생한 generator cap, saline needle cap, $^{99m}Tc$-needle cap, saline vial로 하였고, gamma survey meter를 이용하여 평균값과 표준 편차(mean${\pm}$SD)로 나타냈다. 측정대상물질의 오염유무를 알기 위해 방사선 관리구역에서 반출될 수 있는 물질의 표면오염도인 최대허용표면오염도의 1/10(43.2 cpm)을 기준값으로 정하였다. 각각의 표면오염도를 측정한 결과 방사성의약품 표지를 위해 사용된 생리식염수에서는 $14,429{\pm}26,378$ cpm으로 최대 허용표면오염도의 1/10을 초과하였다. 그리고 측정된 generator중 외산에서는 generator cap: $17{\pm}28$ cpm, saline needle cap: $35{\pm}66$ cpm, $^{99m}Tc$-needle cap: $9{\pm}21$ cpm, saline vial: $13{\pm}28$ cpm으로 최대허용표면오염도의 1/10를 초과하지 않았지만 국산에서는 generator cap: $22,852{\pm}52,545$ cpm, saline needle cap: $87,367{\pm}109,711$ cpm, $^{99m}Tc$-needle cap: $9,008{\pm}10,459$ cpm, saline vial: $186,416{\pm}158,196$ cpm으로 최대 허용표면오염도의 1/10를 초과하였다. 외산 generator에서 발생한 측정대상물질은 일반폐기물로 처분하고 국산 generator와 방사성의약품을 표지하기 위해 사용된 생리식염수는 반드시 방사성폐기물로 간주하여 처분해야 한다. 따라서 일반쓰레기 뿐만 아니라 종합조작실에서 반출되는 모든 물질에 대한 자체적인 방사선측정, 기록 및 비치와 방사성폐기물에 대한 지속적인 교육을 통해 방사성 폐기물이 일반쓰레기로 처분되어 나가는 것을 예방 할 수 있을 것이다.

• 한국세라믹학회지
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• 제43권3호
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• pp.148-151
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• 2006

In order to examine the process parameters for the vitrification of Low and Intermediate Level radioactive Waste (LILW) generated from nuclear power plants, measurements of several melt properties was performed for four selected glasses containing simulated waste. Electrical conductivity and viscosity were determined at temperatures ranging from 1123 to $1673^{\circ}C$. The temperature dependences of both properties in the molten state showed a similar behavior in which their values decrease as the temperature increases. The values of the electrical conductivity and viscosity at a temperature of 1423K adopted in an induction cold crucible melter process were $0.27{\sim}0.42$ S/cm and $9.8{\sim}42$ dPas, respectively.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.336-336
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• 2004

EDTA contained in decontamination wastes can cause complexation of radioactive captions resulting from its various treatment process such as chemical precipitation, and ion exchange etc. It might also import for elevated teachability and higher mobility of cationic contaminants from conditioned wastes such as waste immobilized in cement or other matrices. Therefore, various cheated or unchlelated EDTAS must be treated to environmentally safe materials.(omitted)

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.43-47
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• 2003

The performance of the Radwaste System is measured in terms of generation of waste volumes, the release of radioactive materials to the environment and the occupational radiation exposure to workers. Based on our design and operating experience from PWR plants, various design goals for liquid radwaste system were developed to improve system performance. It has been making continuous effort to develop the advanced liquid radwaste processing technology for new PWR plants since 1998. The primary goal of this effort was to obtain better performance and to design a more economical liquid radwaste system. This paper describes lesson learned experience from design of the liquid radwaste system in Korea Nuclear Power Plants.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 1992년도 가을 학술발표회 논문집
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• pp.174-179
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• 1992

In this paper a discussion is presented about excavation responses of underground openings for radioactive waste disposal. The effects of excavation methods, stress redistribution, thermal change, and backfill materials are reviewed. Comparisons of computational models for discontinuous reek masses and discussions on numerical simulation techniques for the excavation of underground openings are also described. Finally, the application of the CAD system to the planning, design and construction of underground openings fop radioactive waste disposal is introduced.

• Journal of Radiation Protection and Research
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• 제23권4호
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• pp.211-218
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• 1998

감마선원과 피폭자 사이의 거리, 방사선원의 크기 그리고 평균 감마에너지에 따른 외부 감마 피폭선량률의 변화를 분석하였다. 임의 형태로 공기중과 지표에 침적된 방사성물질로부터 외부 감마 피폭선량을 평가하기 위해 개발된 방법을 이용하여 분석을 수행하였다. 공기중의 점선원과 피폭자 사이의 거리가 10 m 이내로 짧은 경우에는 평균 감마에너지가 0.07 MeV에서 피폭선량률이 최소값을 나타내고, 거리가 20 m 이상으로 멀어지면 감마에너지의 증가에 따라 계속적으로 피폭선량률이 증가한다. 반경 40 m 이상의 반구형태의 방사능 구름으로부터 반구의 중심에 위치한 피폭자의 경우에는 감마에너지 증가에 따라 계속적으로 피폭선량률이 증가한다. 지표에 침적된 방사선원으로부터 피폭을 받는 경우에는 지표선원의 면적크기에 상관없이 0.07 MeV에서 최소 피폭선량률이 나타난다. 분석결과 방사선원의 분포형태와 평균 감마에너지가 외부 감마피폭선량의 변화에 큰 영향을 미치고 있음을 알 수 있었다.

• Nuclear Engineering and Technology
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• 제38권6호
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• pp.489-504
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• 2006

A review has been made for the previous studies on safety of a geologic repository for high-level radioactive wastes (HLW) related to autocatalytic criticality phenomena with positive reactivity feedback. Neutronic studies on geometric and materials configuration consisting of rock, water and thermally fissile materials and the radionuclide migration and accumulation studies were performed previously for the Yucca Mountain Repository and a hypothetical water-saturated repository for vitrified HLW. In either case, it was concluded that it would be highly unlikely for an autocatalytic criticality event to happen at a geologic repository. Remaining scenarios can be avoided by careful selection of a repository site, engineered-barrier design and conditioning of solidified HLW. Thus, criticality safety should be properly addressed in regulations and site selection criteria. The models developed for radiological safety assessment to obtain conservatively overestimated exposure dose rates to the public may not be used directly for the criticality safety assessment, where accumulated fissile materials mass needs to be conservatively overestimated. The models for criticality safety also require more careful treatment of geometry and heterogeneity in transport paths because a minimum critical mass is sensitive to geometry of fissile materials accumulation.

• 한국지하수토양환경학회지:지하수토양환경
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• 제21권1호
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• pp.1-5
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• 2016

Capillary barriers, consisting of relatively fine-over-coarse materials, have been suggested as an alternative to traditional compacted soil covers. So, We were analysed to capillary barrier effect according to five cases of multi-layer cover systems. Water balance simulation was conducted with unsaturated flow model HELP to assess unsaturated hydraulic parameters such as hydraulic conductivity, climate affecting the performance of capillary barriers. Simulation were conducted for 5 Cases in the Ulsan area. Result of simulation indicated that three cases was formed unsaturated condition and capillary barrier effect.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2008년도 학술논문요약집
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• pp.338-339
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• 2008