• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.583-584
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• 2005

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.459-465
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• 2017

The goal of this study is to evaluate the effective thermal conductivity and diffusivity of containment walls as heat sinks or passive cooling systems during nuclear power plant (NPP) accidents. Containment walls consist of steel reinforced concrete, steel liners, and tendons, and provide the main thermal resistance of the heat sinks, which varies with the volume fraction and geometric alignment of the rebar and tendons, as well as the temperature and chemical composition. The target geometry for the containment walls of this work is the standard Korean NPP OPR1000. Sample tests and numerical simulations are conducted to verify the correlations for models with different densities of concrete, volume fractions, and alignments of steel. Estimation of the effective thermal conductivity and diffusivity of the containment wall models is proposed. The Maxwell model and modified Rayleigh volume fraction model employed in the present work predict the experiment and finite volume method (FVM) results well. The effective thermal conductivity and diffusivity of the containment walls are summarized as functions of density, temperature, and the volume fraction of steel for the analysis of the NPP accidents.

• 방사성폐기물학회지
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• 제22권2호
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• pp.227-235
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• 2024

After the permanent shut down of Kori Unit 1, various decommissioning activities will be implemented, including decontamination, segmentation, waste management, and site restoration. During the decommissioning period, waste management is among the most important activities to ensure that the process proceeds smoothly and within the expected timeframe. Furthermore, the radioactive waste generated during the operation should be sent to a disposal facility to complete the decommissioning project. Square and cylindrical concrete re-package drums were generated during the 1980s and 1990s. The square, containing boron concentrates, and cylindrical, containing spent resin, concrete re-package drums have been stored in a radioactive waste storage building. Homogeneous radioactive waste, including boron concentrates, spent resin, and sludge, should be solidified or packaged in high-integrity containers (HICs). This study investigates the sequential segmentation process for the separation of contaminated and non-contaminated regions, the re-packaging process of segmented or crushed cement-solidified boron concentrate, and re-packaging in HICs. The conceptual design evaluates the re-packaging plan for the segmented and crushed cement-solidified waste using HICs, which is acceptable in a disposal facility, and the quantity of generated HICs from the treatment process.

• 방사성폐기물학회지
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• 제5권2호
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• pp.91-101
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• 2007

본 연구에서는 원전연료 가공시설에서 발생한 콘크리트 폐기물을 자체처분 하기 위란 국내 규제요건을 검토하였고, 매립 및 재활용에 따른 작업자 및 일반인의 방사선학적 위해도를 평가하기 위해 RESRAD Ver. 6.3, RESRAD BUILD Ver. 3.3 전산코드를 사용하여 피폭선량을 평가하였다. 피폭선량 평가 결과에 따라 유도된 처분제한치는 콘크리트 폐기물 매립의 경우 0.1071Bq/g (3.5% 농축우라늄), 재활용의 경우 $0.05515Bq/cm^2$(5% 농축우라늄)이었다. 또한, 자체처분대상 콘크리트 폐기물의 제염 후 잔류방사능을 조사한 결과, 표면오염도는 전체평균이 $0.01Bq/cm^2$(알파방출체), 콘크리트 폐기물 표면에서 채취한 시료의 방사성핵종 분석결과 $^{238}U$은 0.0297Bq/g, $^{235}U$의 농축도는 2w/o 이하였고, 인위적 오염으로 예상되는 $^{238}U$의 농도는 0.0089Bq/g 이었다. 따라서, 자체처분 대상 콘크리트 폐기물의 매립 및 재활용시 일반인 및 작업자에게 미치는 방사선학적 위해도는 원자력관계법령에서 정하는 처분제한치(개인선량 $10{\mu}Sv/yr$, 집단선량 $1man{\cdot}Sv/yr$) 이하임을 확인하였다.

• Nuclear Engineering and Technology
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• 제47권5호
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• pp.633-645
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• 2015

In order to analyze the mechanical properties of two-way different configurations of prestressed concrete members subjected to axial loading, a finite element model based on the nuclear power plant containments is demonstrated. This model takes into account the influences of different principal stress directions, the uniaxial or biaxial loading, and biaxial loading ratio. The displacement-controlled load is applied to obtain the stress estrain response. The simulated results indicate that the differences of principal stress axes have great effects on the stress-strain response under uniaxial loading. When the specimens are subjected to biaxial loading, the change trend of stress with the increase of loading ratio is obviously different along different layout directions. In addition, correlation experiments and finite element analyses were conducted to verify the validity and reliability of the analysis in this study.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2747-2756
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• 2023

Reinforced Concrete (RC) shear walls are one of the civil structures in nuclear power plants to resist lateral loads such as earthquakes and wind loads effectively. Risk-informed and performance-based regulation in the nuclear industry requires considering possible accidents and determining desirable performance on structures. As a result, rather than predicting only the ultimate capacity of structures, the prediction of performances on structures depending on different damage states or various accident scenarios have increasingly needed. This study aims to develop machine-learning models predicting drifts of the RC shear walls according to the damage limit states. The damage limit states are divided into four categories: the onset of cracking, yielding of rebars, crushing of concrete, and structural failure. The data on the drift of shear walls at each damage state are collected from the existing studies, and four regression machine-learning models are used to train the datasets. In addition, the bagging ensemble method is applied to improve the accuracy of the individual machine-learning models. The developed models are to predict the drifts of shear walls consisting of various cross-sections based on designated damage limit states in advance and help to determine the repairing methods according to damage levels to shear walls.

• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2156-2172
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• 2022

This paper investigates the optimum fiber reinforcement for prestressed concrete containment vessels (PCCVs) under internal pressure. To achieve this aim, steel fiber, which is the most widely used fiber type in current engineering applications, is adopted to constitute steel fiber-reinforced concrete (SFRC) to substitute the conventional concrete in the PCCV. The effects of characteristic parameters, 𝜆_sf, of the steel fiber affecting significantly the mechanical behavior of the concrete are first taken into account. Partial or complete concrete regions of the PCCV are also considered to be replaced by SFRC to balance the economy and safety. By adopting the ABAQUS software, the ultimate bearing capacity and performance for the fiber-reinforced PCCV are scientifically studied and quantified, and the recommendations for the optimum way of fiber reinforcement are presented.

• 한국건설순환자원학회논문집
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• 제5권1호
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• pp.45-52
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• 2017

이 연구에서는 고로슬래그 다량 치환 콘크리트의 원전 콘크리트 적용을 위하여 기존 원전 콘크리트와의 내구성능 비교 및 분석을 수행하였다. 연구결과에 따르면 고로슬래그를 50% 치환한 콘크리트의 압축강도는 초기강도는 기존 원전 콘크리트보다 낮지만, 우수한 장기강도를 나타내었다. 반면, 기존 원전 콘크리트의 초기강도는 높았지만, 장기강도 발현율이 낮게 나타났다. 내구성능의 평가결과, 고로슬래그를 50% 치환한 콘크리트의 내구성능은 모든 평가항목에서 플라이애시 20% 치환 콘크리트와 비교하여 동등이상의 성능을 나타내었다. 특히. 저강도에서의 고로슬래그 50% 치환한 콘크리트는 염해 저항성과 탄산화 저항성, 동결융해 저항성의 향상효과가 뚜렷하게 나타났다. 반면, 감마선 조사에 따른 콘크리트 압축강도와 화학성분의 변화는 미미하게 나타났다.

• 콘크리트학회지
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• 제18권1호
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• pp.71-74
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• 2006

• 콘크리트학회지
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• 제22권6호
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• pp.44-49
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• 2010